nuclear reactor control method and apparatus

专利摘要:
NUCLEAR REACTOR CONTROL METHOD AND APPARATUS A method for controlling a nuclear reactor is presented. The method includes providing a moderator zone in a nuclear reactor core, providing a fuel in the moderator zone and providing one or more housings, each of which has a cavity, adjacent to the fuel. The method also includes allowing a moderator to move between the moderator zone and the cavity of one or more housings in a lower portion of the one or more housings. The method also includes confining the moderator in the cavity of one or more accommodations in an upper portion of the one or more accommodations.
公开号:BR112013029172B1
申请号:R112013029172-9
申请日:2012-05-10
公开日:2020-10-13
发明作者:Neal Mann
申请人:Neal Mann；
IPC主号:

专利说明:

[001] This application claims to benefit from Provisional Patent Application No. U.S. 61 / 485,656, filed on May 13, 2011, which is hereby incorporated by reference. TECHNICAL FIELD
[002] The present disclosure relates to a nuclear reactor control method and apparatus and, more particularly, to a control apparatus and method for controlling a liquid-moderated nuclear reactor. BACKGROUND OF THE INVENTION
[003] Nuclear reactors using conventional nuclear reactor control systems have several shortcomings. Reactors using conventional control systems use constant adjustments to the amount of neutron absorbing material in the reactor core, and have a reduced conversion ratio due to the fact that they absorb an excessive amount of neutrons. In addition, reactors using conventional control systems do not have a relatively large range of reactivity control and therefore use fuel with a relatively narrow range of fissile content. In addition, reactors that use conventional control systems are often refueled, do not capture a large percentage of the potential energy in the fuel, and leave a relatively large amount of radioactive waste per KWH of generated power.
[004] The Canadian Deuterium Uranium (CANDU) reactor control method tried to address some of these problems. However, the CANDU reactor used adjusting rods, which absorbed an excessive amount of neutrons and therefore do not provide a control system to adequately overcome deficiencies in conventional technology.
[005] The present disclosure is aimed at overcoming one or more of the disadvantages presented above and / or other deficiencies in the technique. SUMMARY OF THE INVENTION
[006] According to one aspect, the present disclosure relates to a method for controlling a nuclear reactor. The method includes providing a moderator zone in a nuclear reactor core, providing a fuel in the moderator zone and providing one or more adjacent boxes, each of which has a cavity, adjacent to the fuel. The method also includes allowing the movement of a moderator between the moderator zone and the cavity of one or more adjacent boxes in a lower portion of the one or more adjacent boxes. The method further includes confining the moderator in the cavity of one or more adjacent boxes in an upper portion of the one or more adjacent boxes.
[007] According to another aspect, the present disclosure relates to a nuclear reactor core. The nuclear reactor core has a moderator zone, a fuel arranged in the moderator zone and one or more adjacent boxes arranged adjacent to the fuel, each housing having a cavity. The lower portion of each housing is open for the moderator's movement between the moderator zone and the cavity, and an upper portion of each housing is closed for the moderator's movement between the moderator zone and the cavity. BRIEF DESCRIPTION OF THE DRAWINGS
[008] Figure 1 is a schematic illustration of a nuclear reactor system revealed exemplificative;
[009] Figure 2 is a plan view of a first example reactor of the nuclear reactor system of Figure 1;
[0010] Figure 2A is a stepped plan view of the layout of the nuclear reactor system of Figure 1;
[0011] Figure 3 is a sectional view taken through section A-A of the reactor shown in Figure 2;
[0012] Figure 3A is a stepped sectional view taken through section A-A of the reactor shown in Figure 2;
[0013] Figure 4 is a schematic illustration of an exemplary fuel tube arrangement of the reactor;
[0014] Figure 5 is a side view of the fuel pipe arrangement of Figure 4;
[0015] Figure 6 is a schematic illustration of another exemplary fuel tube arrangement of the reactor;
[0016] Figure 7 is a sectional view taken through section B-B of the reactor shown in Figure 3;
[0017] Figure 8 is a detailed view of an exemplary control cavity matrix of the reactor;
[0018] Figure 8A is another detailed view of an exemplary control cavity matrix of the reactor;
[0019] Figure 8B is another detailed view of an exemplary control cavity matrix of the reactor;
[0020] Figure 8C is a schematic illustration of an exemplary control cavity matrix of the reactor;
[0021] Figure 8D is another schematic illustration of an exemplary control cavity matrix of the reactor;
[0022] Figure 9 is a sectional view of a second exemplary mode of the reactor;
[0023] Figure 10 is a side view of the reactor of Figure 9;
[0024] Figure 11 is a detailed view of an exemplary control cavity matrix of the reactor in Figure 9;
[0025] Figure 12A is a plan view of a third exemplary reactor modality;
[0026] Figure 12B is a sectional view of the third example of the reactor;
[0027] Figure 12C is a perspective view of the third example of the reactor;
[0028] Figure 12D is a schematic illustration of the third exemplary mode of the reactor;
[0029] Figure 12E is another schematic illustration of the third example of the reactor;
[0030] Figure 12F is another schematic illustration of the third exemplary mode of the reactor;
[0031] Figure 12G is another perspective view of the third exemplary modality of the reactor;
[0032] Figure 12H is a plan view of a fourth exemplary reactor modality;
[0033] Figure 121 is a schematic sectional view of the fourth exemplary mode of the reactor;
[0034] Figure 12J includes both a schematic plan view and a schematic sectional view of the fourth exemplary reactor modality;
[0035] Figure 12K is a schematic sectional view of the fourth exemplary mode of the reactor;
[0036] Figure 12L includes both a schematic plan view and schematic sectional views of the fourth exemplary reactor modality;
[0037] Figure 12M includes both a schematic plan view and schematic sectional views of the fourth exemplary reactor modality;
[0038] Figure 12N includes a schematic sectional view of the fourth exemplary reactor modality;
[0039] Figure 13 is a schematic illustration of an exemplary reactor refrigerant subsystem;
[0040] Figure 14 is a sectional view of an exemplary passage of the reactor refrigerant subsystem;
[0041] Figure 15 is a sectional view taken through section C-C of the reactor control subsystem shown in Figure 20;
[0042] Figure 16 is a schematic illustration of a first exemplary auxiliary refrigerant subsystem;
[0043] Figure 17 is a schematic illustration of a second exemplary auxiliary refrigerant subsystem;
[0044] Figure 18 is a plan view of the second auxiliary refrigerant subsystem of Figure 17;
[0045] Figure 19 is a schematic illustration of a third exemplary auxiliary refrigerant subsystem; and
[0046] Figure 20 is a schematic illustration of an exemplary reactor control subsystem. DETAILED DESCRIPTION OF THE INVENTION
[0047] Figure 1 illustrates an exemplary nuclear reactor system 5 to generate power from a nuclear reaction. The nuclear reactor system 5 can include a power generation subsystem 10 and a reactor 15. The reactor 15 can supply energy from a nuclear reaction to the power generation subsystem 10. The nuclear reactor system 5 can also include a exchanger heat exchanger 20, a reactor refrigerant subsystem 25 and a pump subsystem 30. The reactor refrigerant subsystem 25 can facilitate the heat exchange between the reactor 15 and the heat exchanger 20, and the pump subsystem 30 can pressurize the reactor refrigerant subsystem 25. The nuclear reactor system 5 can additionally include an auxiliary refrigerant subsystem 35 and a reactor control subsystem 40. The auxiliary refrigerant subsystem 35 can provide additional heat transfer from reactor 15, and the reactor control subsystem 40 can control a reactor operation 15.
[0048] The power generation subsystem 10 may include one or more turbines 45, one or more drive assemblies 50, one or more generators 55, a turbine cooling subsystem 60 and a turbine steam subsystem 65. The turbine 45 can drive generator 55 via drive assembly 50. Turbine steam subsystem 65 can transfer water (H2O) and steam (H2O) between turbine 45 and turbine cooling subsystem 60.
[0049] Turbine 45 can be any type of turbine that is suitable for use with a nuclear reactor such as, for example, a steam turbine. The turbine 45 can convert the high pressure steam (H2O) that is released by the turbine steam subsystem 65 into mechanical energy. For example, turbine 45 may include a plurality of elements mounted on a rotating axis. The high pressure steam (H2O) can enter the turbine 45 and pass over the elements mounted on the shaft, the kinetic energy of the steam (H2O) thereby forcing the plurality of elements to rotate the rotating axis. The turbine 45 may include a series of one or more high pressure cylinders followed by one or more low pressure cylinders. Each cylinder can admit steam (H2O) in a central portion, and the steam (H2O) can progressively expand through the series of cylinders, thus moving the elements mounted on the axis of the turbine 45. The turbine 45 can include stationary elements that direct a flow of steam (H2O) within turbine 45. Turbine 45 may include additional systems such as, for example, a hydraulic control valve system that has oil operated valves to regulate the flow of steam (H2O), a lubrication system to lubricate the bearings that support the cylinders, and a moisture separator to remove moisture from the steam (H2O) after leaving the high pressure cylinders and before entering the low pressure cylinders.
[0050] The drive assembly 50 can be any assembly suitable for transferring mechanical energy from turbine 45 to generator 55 such as, for example, a mechanical drive shaft assembly. The drive assembly 50 can operably connect a rotating shaft of the turbine 45 to the generator 55 so that the kinetic energy from the steam (H2O) that reaches the elements mounted on the shaft of the turbine 45 can be transferred as mechanical energy to the generator 55 via drive assembly 50.
[0051] Generator 55 can be any type of generator that is suitable for use with a nuclear reactor such as, for example, an electric generator. For example, generator 55 may include a wire and magnet arrangement for generating electricity from the mechanical energy transferred through drive assembly 50. For example, drive assembly 50 may rotate a magnetic element within generator 55 to generate power electrical. Generator 55 can produce AC electricity at any suitable frequency such as, for example, 50 Hz (50 cycles) or 60 Hz (60 cycles) power. The power generation subsystem 10 can be operated to maintain one or more generators 55 at a substantially constant frequency such as, for example, 50 or 60 cycle power.
[0052] The turbine cooling subsystem 60 can be any type of cooling system that is suitable for use with a nuclear reactor such as, for example, a cooling system that uses condensers, cooling towers and / or airflow forced to heat exchange. The turbine cooling subsystem 60 can remove excess steam (H2O) from turbine 45 and condense excess steam (H2O) into water (H2O). In addition to using condensers, cooling towers and / or forced air flow to condense steam (H2O) into water (H2O), the turbine cooling subsystem 60 can also use nearby bodies of water (H2O), if available and suitable for, for example, single-pass cooling.
[0053] The turbine steam subsystem 65 can be any type of arrangement suitable for transferring water (H2O) and steam (H2O) between heat exchanger 20, turbine 45 and turbine cooling subsystem 60. O turbine steam subsystem 65 may include a passage 70 that transfers hot steam (H2O) from heat exchanger 20 to turbine 45, a passage 75 that transfers inoperative or surplus steam (H2O) from turbine 45 to the turbine cooling subsystem 60, and a passage 80 that transfers relatively cold water (H2O) from the turbine cooling subsystem 60 to the heat exchanger 20. Passages 70, 75 and 80 can be any suitable passages for transferring steam (H2O) and water (H2O) such as, for example, steel piping.
[0054] The nuclear reactor system 5 can also supply steam (H2O) for any other suitable purpose for which steam (H2O) can be useful, in addition to supplying steam (H2O) to the turbines for power generation. For example, nuclear reactor system 5 may include configurations in which steam (H2O) is not returned to the system after use and / or in which the incoming water (H2O) comes from a source that is different from the steam subsystem turbine 65. For example, nuclear reactor system 5 can supply steam (H2O) for use in the extraction of geothermal oil.
[0055] Heat exchanger 20 can be any type of heat exchanger suitable for transferring thermal energy between power generation subsystem 10 and reactor 15. For example, heat exchanger 20 can include one or more steam generators which have a plurality of tubes through which the hot reactor refrigerant from the reactor refrigerant subsystem 25 flows. Each steam generator can include, for example, thousands of tubes to receive the hot reactor refrigerant. For example, each steam generator can include between approximately 3,000 and approximately 16,000 tubes. The hot reactor refrigerant flowing through the steam generator tubes can boil water (H2O) delivered to the heat exchanger 20 through the turbine steam subsystem 65. The steam (H2O) generated by the heat exchanger steam generators 20 can then be transferred to turbine 45 via turbine steam subsystem 65. While passing through heat exchanger 20, the reactor refrigerant can be cooled and can subsequently be returned to reactor 15 via subsystem of reactor refrigerant 25.
[0056] The water (H2O) delivered to the heat exchanger 20 through the turbine steam subsystem 65 can enter the heat exchanger 20 in an upper portion of the heat exchanger 20. The relatively cold water (H2O) can be injected in an interior portion of the heat exchanger 20 by means of a plurality of nozzles 83 (see Figure 20) which can be arranged in an upper and / or central portion of the heat exchanger 20, on the interior walls of the heat exchanger 20. A plurality of nozzles 83 can be oriented downwards and can inject water (H2O) into the boiling water (H2O) already contained within the heat exchanger 20. Therefore, the relatively cold water (H2O) can be mixed with the boiling water (H2O) ) already contained in the heat exchanger 20, thereby helping to reduce a magnitude of a H2O temperature gradient contained within the heat exchanger 20. Thus, the heat exchanger 20 may be able to produce steam (H2O) in higher temperatures due to gradi lower temperature. It is envisaged that the magnitude of the temperature gradient can also be further reduced by using a recirculation pump or by using a combination of convection currents, with entrained boiling water (H2O) in the currents below relatively cold water ( H2O) from nozzles 83.
[0057] Reactor 15 can be any type of nuclear reactor suitable for generating power from a nuclear reaction. Reactor 15 can be, for example, any nuclear reactor that uses liquid moderator. In addition, for example, reactor 15 may be a reactor cooled by heavy water and / or moderated by heavy water. Reactor 15 can be, for example, a CANDU reactor. As illustrated in Figure 2, reactor 15 can include a containment structure 85, a pressure vessel 90, a reflecting zone 95 and a reactor core 100. The containment structure 85 and pressure vessel 90 can accommodate the reflecting zone 95. The reactor core 100 can be arranged in the reflective zone 95.
[0058] The containment structure 85 can be any type of structure suitable for housing the reflecting zone 95 and the reactor core 100, and to protect the environment outside the reactor 15 from radiation and neutrons emitted through the reactor 15. For For example, the containment structure 85 can include prestressed concrete or reinforced concrete walls that surround the reflective zone 95 and the reactor core 100. The containment structure 85 can have walls that are of any suitable thickness to accommodate the reflective zone 95. and the reactor core 100 such as, for example, between approximately 1.21 m (four feet) and approximately 3.04 m (ten feet). The containment structure 85 can include openings for receiving various elements of the reactor refrigerant subsystem 25, auxiliary refrigerant subsystem 35, or other elements of the nuclear reactor system 5. The containment structure 85 can structurally support, insulate and serve as a radiation barrier for the reflecting zone 95 and the reactor core 100. A water mirror can, for example, simply fill the bottom of the pressure vessel 90, or it can be enclosed in separate containers as further described below.
[0059] Pressure vessel 90 can be any type of pressure vessel or structure suitable for pressurizing the reflective zone 95 and reactor core 100. For example, pressure vessel 90 may be a steel vessel that seals and pressurizes the reflecting zone 95 and the reactor core 100. The pressure vessel 90 may include one or more steel elements that are configured and / or connected to form a sealed vessel. Pressure vessel 90 may include any other suitable material with properties suitable for use as a pressure vessel such as, for example, materials that have resistance to fracture and embrittlement. Pressure vessel 90 can be used when reflective zone 95 and reactor core 100 include a "hot moderator" that is maintained at a relatively high temperature. Pressure vessel 90 may include openings for receiving various elements of reactor refrigerant subsystem 25, auxiliary refrigerant subsystem 35, or other elements of nuclear reactor system 5. Pressure vessel openings 90 may be sealed to maintain a pressurization of the reflective zone 95 and the reactor core 100 within the pressure vessel 90.
[0060] As shown in Figure 3, the reflecting zone 95 can include a water mirror 105 and a steam area 110. A boundary 115 can separate the water mirror 105 and the steam area 110.
[0061] The water mirror 105 may include a moderator in a liquid state. For example, the water mirror 105 may include D2O ("heavy water") in a liquid state. The water mirror 105 may include D2O manufactured to have any properties suitable for moderating a nuclear reaction. For example, the D2O of the water mirror 105 can be heavy water for use in a reactor (99.75% pure). The water mirror 105 may also include H2O moderator ("light water") in a liquid state. The water mirror 105 can include a "hot moderator" (for example, in Figure 2) or a "cold moderator" (for example, in Figure 11).
[0062] The steam area 110 can include a moderator that is the same material as the water mirror 105. The steam area 110 can include the moderator that is in a gaseous state. The heat from the reactor core 100 can heat the moderator in the reflective zone 95, causing part of the moderator to be retained in a gaseous state in the steam area 110. The temperature of the gaseous moderator in the steam area 110 is approximately the same as a temperature of the liquid moderator of the water mirror 105. The vapor area 110 can fill substantially the entire reflective zone 95 if substantially the entire moderator is heated to a gaseous state. In addition, the water mirror 105 can substantially fill the entire reflective zone 95 if substantially the entire moderator is cooled to a liquid state. A limit 115 can separate the water mirror 105 and the steam area 110.
[0063] Four exemplary embodiments of a reactor core are disclosed below: reactor core 100, reactor core 100 ', reactor core 100a and reactor core 100b. Where appropriate, the various resources revealed from each exemplary modality (for example, the reference numbers that have a "a" modifier for reactor core 100a) can be combined with resources from the other modalities. As further revealed below, the exemplary embodiments disclosed illustrate the wide range of possible modalities of the disclosed nuclear reactor system. For example, reactor core 100, 100 ', 100a and 100b show that the revealed nuclear reactor system can include both horizontal and vertical fuel tube arrangements, both cold and hot moderator in the reactor core, different nuclear fuels such as uranium, plutonium and thorium in different compositions such as metal, oxide or salts, different fuel tube arrangements such as square or hexagonal arrangements, different types of moderator (eg D2O and H2O), different primary refrigerants (eg , liquids such as D2O, H2O and organic fluids; molten metals such as sodium and lead; molten salts and gases such as helium) and sets of different moderator cooling procedures (for example, heat exchange and direct fluid exchange) . Considering the exemplary modalities shown below, an individual of ordinary skill in the art can understand that the various features revealed from each exemplary modality can be combined with the resources of any other exemplary modality, where appropriate.
[0064] According to the first exemplary embodiment of the reactor core, the reactor core 100 may include a fuel assembly 125 and a control cavity matrix 130. The control cavity matrix 130 may contain one or more moderator pockets and / or moderator steam adjacent to fuel assembly 125. Fuel tubes 135 can be oriented vertically in a square matrix with truncated corners (as shown in Figure 4), and the fuel moderator and coolant can be heavy water (for example , OF) . The moderator can be cooled by driving from a portion of the primary refrigerant flow (fuel refrigerant).
[0065] Fuel assembly 125 can be any type of nuclear fuel suitable for use in a nuclear reaction. For example, fuel assembly 125 may include bundles of fuel rods that are arranged in a plurality of fuel pipes 135. For example, fuel assembly 125 may include an arrangement of hundreds of fuel pipes 135. For example, the fuel assembly 125 may include between approximately 100 and approximately 500 fuel tubes 135 which may be approximately 10.16 cm (four inches) in diameter. Each fuel tube 135 can include any suitable number of fuel bundles such as, for example, 12 fuel bundles. Each fuel bundle can include any suitable number of fuel rods such as, for example, 37 fuel rods. The fuel assembly 125 can include any fuel suitable for a nuclear reaction such as, for example, natural uranium, enriched uranium, mixed oxide fuel (MOX), plutonium, thorium and / or various mixtures of these and other materials. For example, fuel assembly 125 may include mixed uranium / plutonium fuel or mixed uranium / thorium fuel.
[0066] Fuel assembly 125 may include fuel pipes 135 that are arranged vertically (for example, as shown in Figure 2). The fuel assembly 125 may include fuel tubes 135 arranged in any suitable configuration such as, for example, a right angle matrix as shown in Figures 4 and 5.
[0067] With reference again to Figure 2, the control cavity matrix 130 can include a three-dimensional control cavity matrix 140. For example, the three-dimensional control cavity matrix 140 can serve as a housing to confine the moderator adjacent to the fuel tubes 135 of fuel assembly 125. As shown in Figures 2, 3 and 7, the plurality of control cavities 140 can be arranged horizontally to each other, as well as be stacked vertically. Control wells 140 can be scaled vertically and / or horizontally within the control well matrix 130. For example, the vertical scaling of control wells 140 is shown in Figure 3. Control wells 140 can be arranged in any configuration suitable to confine a moderator adjacent to the 135 fuel pipes.
[0068] Figures 2A and 3A illustrate different views of reactor 15 arrangements. Figures 2A and Figure 3A provide views of exemplary scale arrangements of reactor 15.
[0069] As shown in Figures 2 and 8, each control cavity 140 can include a structural assembly 145 and a cone assembly 150. Cone assembly 150 can confine the moderator within structural assembly 145. Structural assembly 145 can serve as an accommodation to confine the moderator.
[0070] As shown in Figures 2, 3 and 7, structural assembly 145 may include one or more upper members 155, one or more side members 160, one or more end members 165 and one or more intermediate members 170. The members upper 155, side members 160, end member 165 and intermediate member 170 can be formed from any structural materials suitable for confining the moderator such as, for example, zirconium alloy. The upper members 155, the side members 160, the end member 165 and the intermediate member 170 can be attached to each other by any suitable set of procedures such as, for example, welding. The upper members 155, the side members 160, the end member 165 and the intermediate member 170 can also be integrally formed with each other. The upper limbs 155, the side members 160, the end member 165 and the intermediate member 170 can be any structural member suitable for confining the moderator such as, for example, members similar to the plate and / or substantially flat. The upper members 155 can be, for example, a flat member substantially and horizontally disposed in an upper portion of the control cavity 140, and can be attached to the substantially flat side members 160. The end members 165 can be attached to the end portions of the upper limb 155 and of the side members 160. The upper members 155, the side members 160 and the end members 165 can be fixed to form, for example, a cavity that has a closed upper portion and an open bottom portion. In this way, the upper limb 155, side members 160 and end members 165 can substantially prevent movement of the moderator in and out of an upper portion of the control cavity 140, while allowing the moderator to move in and out. out of a lower portion of the control cavity 140. The upper portion of the control cavity 140 may include the upper limb 155, the upper portions of the side members 160 and the upper portions of the end members 165. The lower portion of the control cavity 140 control 140 may include the lower portions of the side members 160 and the lower portions of the end members 165.
[0071] One or more intermediate members 170 can be arranged between and attached to the side members 160 and the upper member 155. The intermediate members 170 can be arranged at any interval along the control cavity 140. The intermediate members 170 can substantially prevent the movement of the moderator through the control cavity 140 in an upper portion of the control cavity 140. The end members 165 and the intermediate members 170 may have a height that is less than a height of the side members 160. The side members 160 of a given control cavity 140 can be attached to the upper limb 155 of another control cavity 140 arranged below, for example, in the case where the control cavities 140 are stacked vertically. Due to the fact that the height of the end members 165 and the intermediate members 170 may be less than the height of the side members 160, the moderator may be free to move under the end members 165 and the intermediate members 170 by through the gaps 175 and the gaps 180, respectively, as shown in Figure 7. In this way, the end members 165 and the intermediate members 170 can serve as deflectors to block the moderator's movement in an upper portion of the control cavity 140 and allow movement of the moderator in a lower portion of control cavity 140. Spans 180 may allow movement of the moderator through a lower portion of control cavity 140 and spans 175 may allow movement of the moderator between reflective zone 95 and the control cavity 140. The moderator cannot move under the side members 160, which can be attached to the upper limb 155 of the control cavity 140 arranged below O. However, it is contemplated that the gaps can be provided between the side members 160 and the upper member 155 of the control cavity 140 disposed below, to also allow the movement of the moderator under part or all of the side members 160. Thus, it is contemplated it should be noted that the moderator can be free to move between the reflective zone 95 and the control cavities 140, under the side members 160.
[0072] As shown in Figures 3 and 7, the control cavities 140 can include the same moderator as the reflective zone 95, due to the fact that the moderator can be free to move between the reflective zone 95 and the control cavities 140 through spans 175 and 180. As the moderator confined in control cavity 140 is heated through neutrons, gamma radiation and / or thermal conduction from fuel tubes 135, part or all of the moderator in the cavity of Control 140 can be heated to a gaseous state in a gas zone 185. Part or all of the moderator in control cavity 140 can also be in a liquid state in a liquid zone 190. Gas zone 185 and liquid zone 190 can be separated by a 195 boundary. The size of gas zone 185 and liquid zone 190 may vary between control cavities 140 and between different intermediate members 170 within a single control cavity 140. Thus, the location of boundary 195 can vary between control cavities 140 and between different intermediate members 170 within a single control cavity 140. For example, a given control cavity 140 can have both a gas zone 185 and a liquid zone 190, substantially only one zone gas 185, or substantially only a liquid zone 190.
[0073] The heat imparted by means of neutrons, gamma radiation and / or conduction from the fuel tubes 135 can cause the liquid moderator of the liquid zone 190 to be maintained at a temperature at or just below the boiling point of the moderator . For example, the moderator of the liquid zone 190 can be kept in a latent state. As the moderator in the liquid zone 190 boils slightly, part of the moderator can evaporate and rise to the gas zone 185. In addition, the moderator in the gas zone 185 that is close to the components of the reactor refrigerant subsystem 25 (for example, as described below) can condense and drip back into liquid zone 190 along the internal surfaces of control cavity 140. The size of gas zone 185 can therefore remain substantially constant, and limit 195 can remain relatively stationary when the amount of heat imparted through the fuel pipes 135 and the amount of heat removed through the reactor refrigerant subsystem 25 are substantially the same. As further described below, the size of the gas zone 185 and a position of the boundary 195 can vary slightly over short periods of time (for example, over a period of days) based on the absorption of samarium and neutron xenon, and can vary significantly for long periods of time (for example, over a period of years), based, for example, on an aging (for example, depletion) of the fuel. The size of the gas zone 185 and the position of the limit 195 may vary slightly during and briefly after periods of change in the cooling rate through the reactor refrigerant subsystem 25.
[0074] As shown in greater detail in Figure 8, cone assembly 150 can include an internal cone assembly 200, an external cone assembly 205 and a passage 210. Cone assemblies 150 can provide a structural interface between tubes fuel 135, which can pass through control cavities 140, and can help to distribute heat evenly from fuel tubes 135 within control cavities 140. The inner cone assembly 200 can surround a portion of the fuel tube 135, outer cone assembly 205 may surround inner cone assembly 200 and passageway 210 may be arranged between inner cone assembly 200 and outer cone assembly 205.
[0075] The inner cone assembly 200 may include a cone 215 that may surround a portion of the fuel tube 135. The cone 215 may be formed from any material suitable to confine the liquid moderator or vapor moderator within the cavity of control 140 such as, for example, zirconium alloy. The cone 215 can be formed from separate elements or it can be integrally formed as a single element. Cone 215 may also have any height suitable for confining the moderator. For example, cone 215 can have a height that is approximately twice the height of control cavity 140. Cone 215 can pass through an opening that is formed in upper member 155 of structural assembly 145. Cone 215 can be arranged in each control cavity 140. Due to the fact that cone 215 can have a height that is greater than a height of control cavity 140, cone 215 can overlap with other cones 215 that surround the same fuel tube 135 Cone 215 can form a passage 220 with fuel tube 135 and overlapping cones 215 can form a passage 225 with each other. Passage 220 can be a continuation of pass 225. Passages 220 and 225 can surround fuel tubes 135 and can be of any suitable shape such as, for example, conical shaped passages. The cone 215 can be sealed to the fuel pipe 135 at the top of the cone 215 so that the passage 220 can be a dead end, with the passage 220 being sealed at the top. Due to the fact that fuel pipe 135 can normally be hotter than the moderator's boiling point, any moderator in passage 220 may boil and the resulting vapor moderator will force the liquid moderator down out of the bottom of passages 220 and 225 through a gap 250 and to the bottom portion of the control cavity 140. Due to the fact that steam can drive value less effectively than the liquid moderator, the resulting double steam gap formed through passages 220 and 225 and overlapping cones 215 can reduce heat transfer from fuel tubes 135 to the moderator in control cavity 140. In this way, cones 215 can effectively surround fuel tubes 135 with a thin layer of steam moderator at passages 220 and 225, with the steam moderator in fluid communication with the reflective zone 95.
[0076] The outer cone assembly 205 may include an inner cone 235 and an outer cone 240. The inner cone 235 and the outer cone 240 may be of a similar material to cone 215 and may surround the fuel pipe 135 and the cone 215. The inner cone 235 can be attached to a lower surface 245 of the upper limb 155 and can be fixed intermittently to the bottom of the inner cone 235 to the bottom of the cone 215 for structural integrity, while still leaving a gap 230 that can allow vertical flow of the liquid moderator from the bottom of a cavity 140 through passage 210 to the cavities 140 above and below. The inner cone 235 can have a height that is slightly less than a height of the control cavity 140, and can form the gap 250 with an upper surface 255 of an adjacent control cavity 140 which is arranged below. The outer cone 240 may also be attached to the lower surface 245 of the upper limb 155 and may have a height that is less than a height of the inner cone 235. The cavity 260 may be formed between the inner cone 235 and the outer cone 240. The moderator can be free to move between the liquid zone 190 of the control cavity 140 and the cavity 260. The moderator can also be free to move between the liquid zone 190 and a portion 270 disposed between the adjacent outer cones 240 of the tubes adjacent fuel tanks 135. The liquid zone 275 that includes the liquid moderator can be arranged in cavity 260. As fast neutrons and gamma radiation from fuel tubes 135 heat the moderator in control cavity 140, the liquid moderator in the liquid zone 275 can be heated in the steam moderator and can form a gaseous zone 280. In addition, as higher velocity neutrons (for example, fast) and gamma radiation from fuel tubes 135 heat up the moderator in the control cavity 140, the liquid moderator in the liquid zone 190 can be heated in the steam moderator and can form a portion of the gas zone 185 within the portion 270 disposed between the adjacent outer cones 240. Depending on the amount of heat imparted through of higher velocity neutrons (for example, fast) and gamma radiation from fuel tubes 135, cavity 260 and portion 270 can be substantially and entirely filled by gas zone 280 and 185, respectively, or can be substantially and entirely filled by the net zone 275 and 190, respectively.
[0077] A limit 290 can separate liquid zone 275 and gas zone 280 and limit 195 can separate liquid zone 190 and gas zone 185. Liquid zone 275, gas zone 280 and limit 290 can have similar characteristics the characteristics of liquid zone 190, gas zone 185 and limit 195, respectively, discussed above. For example, the size of gaseous zones 280 and 185 may remain substantially constant, and limits 290 and 195 may remain relatively stationary, when the amount of heat imparted by the higher velocity neutrons (for example, fast) and gamma radiation from fuel pipes 135 and the amount of heat removed by the reactor refrigerant subsystem 25 is substantially the same.
[0078] Passage 210 may be formed between cone 215 and inner cone 235. A gap 300 may be formed between a lower cone portion 215 and an inner lower cone portion 235. The moderator may be free to move between the passage 210 and a lower portion of the control cavity 140 through the gap 300, which can be similar to the gap 230. Thus, due to the fact that the control cavity 140 can be in fluid communication with the reflective zone 95, the moderator can be free to move between passage 210 and the reflecting zone 95 via control cavity 140. Due to the fact that passage 210 cannot be closed at the top, passage 210 can be filled substantially with the moderator liquid and steam bubbles from the moderator can rise quickly through it.
[0079] Figures 8A, 8B, 8C and 8D illustrate alternative views of cone assembly 150.
[0080] Figures 9, 10 and 11 illustrate a second exemplary embodiment of reactor 15. In this embodiment, reactor 15 may include a reactor core 100 'disposed in reflective zone 95. Reactor core 100' may include an assembly of fuel 125 'and a control cavity matrix 130'. The control cavity matrix 130 'can confine the moderator adjacent to the fuel assembly 125'. In this second embodiment, the fuel tubes 135 'can be arranged horizontally and arranged in a square matrix with truncated corners, as shown in Figure 10. The moderator can be cold and can be cooled by pumping relatively the cooler moderator into the cavities of control 140 '. The moderator can be heavy water (D2O), and the composition of the primary refrigerant can be any suitable refrigerant.
[0081] Fuel assembly 125 'may include a plurality of fuel pipes 135'. The fuel lines 135 'can be similar to the fuel lines 135 of the reactor core 100. The fuel lines 135' can, for example, be arranged substantially and horizontally.
[0082] The control cavity matrix 130 'may include a plurality of control cavities 140'. As shown in the end view of the reactor core 100 'shown in Figure 10, the control cavities 140' can be arranged between the fuel tubes 135 'of the fuel assembly 125'. Each control cavity 140 'can be included in a structural assembly 145' which can be a tube that is longer than the length of the fuel assembly 125 ', and can contain control cavities 140' which can serve as boxes adjacent to confine the moderator.
[0083] As shown in Figures 9 and 11, structural assembly 145 'can include one or more upper members 155', one or more end members 165 'and one or more intermediate members 170', which can be formed from similar materials and fixed through sets of similar procedures as the members of the structural assembly 145 of the control cavity 140. The upper members 155 'can have, for example, a curved shape that surrounds an upper portion of the control cavity 140'. For example, the upper limb 155 'may have a semicircular shape that surrounds an upper portion of the control cavity 140'. In addition, for example, the upper limb 155 'can have a substantial and completely circular shape with a lower portion 160', so that the upper limb 155 'which continues in the lower portion 160' can completely surround the control cavity 140 ' . The end members 165 'can be attached to the end portions of the upper member 155' and the lower portions 160 'to completely surround the control cavities 140'. Structural assembly 145 'can extend beyond the length of the fuel rods (which can be arranged in fuel tubes 135') to include end compartments 142 '. End members 165 'may have a passageway 166' which is in fluid communication with vertical tubing 167 ', which may allow the liquid moderator to flow out near the top of end compartments 142', and may allow that the moderator steam flows freely in both directions between the end compartments 142 'and the vertical pipeline 167'. The lower end of the vertical pipe 167 'can lead to the moderator reservoir 168', which can contain both the liquid moderator and the moderator vapor. When the upper limb 155 'is, for example, a semicircular shape, the upper limb 155' and intermediate members 170 'can form a cavity that has a closed upper portion and an open bottom portion. In this way, the upper limb 155 'and the intermediate members 170' can substantially prevent the moderator from moving in and out of an upper portion of the control cavity 140 ', while allowing the moderator to be free to move in and out. out of a lower portion of the control cavity 140 '. When the upper limb 155 'is, for example, a substantially complete circle, the intermediate members 170' can only cover an upper portion of an open circular cross section formed by the upper limb 155 'which includes the lower portion 160'. In this way, the intermediate members 170 'and the upper member 155' having the lower portion 160 'can substantially prevent movement of the moderator in and out of an upper portion of the control cavity 140', while allowing the moderator to move. move in and out of a lower portion of control cavity 140 '.
[0084] One or more intermediate members 170 'can be arranged between and fixed to an inner surface of the upper member 155'. The intermediate members 170 'can be arranged at any interval along the control cavity 140'. Intermediate members 170 'can substantially prevent movement of the moderator through control cavity 140' in an upper portion of control cavity 140 '. The intermediate members 170 'may have a height that is less than a height of the control cavity 140'. In this way, the intermediate members 170 'can serve as deflectors to block the movement of the moderator in an upper portion of the control cavity 140' and allow the movement of the moderator in a lower portion of the control cavity 140 '. The moderator can be free to move through a lower portion of the control cavity 140 'by moving under the intermediate members 170', and can move between the reflective zone 95, the end compartments 142 'and the control cavity 140 'moving under intermediate members 170'.
[0085] As shown in Figures 9 and 11, control cavities 140 'can include the same moderator as the moderator in end compartments 142', due to the fact that the moderator can move between the reflective zone 95 and the cavities control unit 140 '. As the moderator confined in control cavity 140 'is heated by neutrons, gamma radiation and the thermal conduction of fuel tubes 135', some or all of the moderator in control cavity 140 'can be heated to a gaseous state in a gas zone 185 '. Part or all of the moderator in control cavity 140 may also be in a liquid state in a liquid zone 190 '. The gas zone 185 'and the liquid zone 190' can be separated by a boundary 195 '. The size of gas zone 185 'and liquid zone 190' can vary between control cavities 140 ', and between different intermediate members 170' within a single structural assembly 145 '. Thus, the location of boundary 195 'can vary between control cavities 140' and between different intermediate members 170 'within a single structural assembly 145'. For example, a given control cavity 140 'may have either a gas zone 185' or a liquid zone 190 ', substantially only a gas zone 185', or substantially only a liquid zone 190 '.
[0086] Liquid zone 190 ', gas zone 185' and limit 195 'may have characteristics similar to the characteristics of liquid zone 190, gas zone 185 and limit 195, respectively, discussed above with reference to control cavity 140 For example, the size of gas zone 185 'can remain substantially constant, and limit 195' can remain relatively stationary when the amount of heat imparted through fast neutrons, gamma radiation, and the conduction of fuel tubes 135 ' and the amount of heat removed by the reactor refrigerant subsystem 25 is substantially the same.
[0087] Figures 12A to 12F illustrate a third alternative exemplary modality of reactor 15. This modality includes a hexagonal array of vertical fuel tubes (for example, as illustrated in Figures 12A and 6) and a hot moderator that can be cooled by pumping the hot moderator from a water mirror, cooling the hot moderator, and pumping the moderator back into the reactor core and control cavities via the reactor refrigerant subsystem 25. In this mode (as illustrated in Figure 12F), each control cavity assembly can fit vertically into the space bounded by the four vertical fuel tubes. As shown in Figure 12B, this embodiment can include a reactor core 100a.
[0088] The reactor core 100a may include a fuel assembly 125a that is similar to the fuel assembly 125, and a control cavity matrix 130a. The control cavity matrix 130a may contain a moderator pocket and / or moderator vapor adjacent to the fuel assembly 125a. In this embodiment, as described more fully below, a moderator refrigerant tube 335a can have small orifices 337a arranged in the lenses and extending along a length of the moderator refrigerant tube 335a, and control cavities 140a can be cooled through a relatively cooler moderator sprayer sprayed from the moderator refrigerant tube 335a.
[0089] The control cavity matrix 130a can include a three-dimensional matrix of the control cavities 140a. For example, the three-dimensional array of control cavities 140a can serve as a housing for compartmentalizing and / or confining the moderator pockets adjacent to fuel tubes 135a of fuel assembly 125a. As shown in Figures 12A to 12F, the plurality of control cavities 140a can be arranged in vertical stacks with the stacks arranged horizontally to each other as well as being stacked vertically. As shown in Figure 12E, control cavities 140a can be scaled vertically within the control cavity matrix 130a. Control cavities 140a can be arranged in any suitable configuration to confine the moderator pockets and / or the moderator vapor adjacent to the fuel tubes 135a.
[0090] As shown in Figures 12C to 12F, each control cavity 140a can include the moderator refrigerant tube 335a, an approximately tapered upper member 155a and a side member 160a. As shown, side member 160a can be approximately trapezoidal (for example, in the illustrated hexagonal fuel tube matrix) with toothed corners 161a for fuel tubes 135a or approximately square (not shown) for a square fuel tube matrix. The upper limbs 155a can be joined without gaps to the side member 160a and the moderator refrigerant tube 335a to confine a pocket of the moderator and / or the moderator vapor adjacent to the fuel tubes 135a. The moderator may be free to move to or from the control cavity 140a through the open bottom of the control cavity 140a and through a gap 162a between the bottom of a given side member 160a and the top of the side member 160a from the cavity below.
[0091] The upper limbs 155a, the side limb 160a and the moderator refrigerant tube 335a can be formed from any suitable structural materials to direct the moderator's movement and / or confine the moderator such as, for example, alloy zirconium. The upper members 155a, the side member 160a and the moderator refrigerant tube 335a can be attached to each other by any suitable set of procedures such as, for example, welding. The upper limbs 155a, the side limb 160a and the moderator refrigerant tube 335a can also be integrally formed with each other. The upper limbs 155a, the side limb 160a and the moderator refrigerant tube 335a can be attached to form, for example, a cavity that has a closed upper portion and an open bottom portion. In this way, the upper limb 155a, the lateral limb 160a and the moderator refrigerant tube 335a can substantially prevent the moderator from moving in and out of an upper portion of the control cavity 140a, while allowing the moderator to be free to move in and out of a lower portion of control cavity 140a. The upper portion of the control cavity 140a may include the upper limb 155a, the upper portions of the lateral limb 160a and the portions of the moderator refrigerant tube 335a. The lower portion of the control cavity 140a may include the lower portions of the side member 160a and the portions of the moderator refrigerant tube 335a.
[0092] The span 162a can allow the moderator to move between the reflecting zone 95 and the control cavity 140a, directly or through a gap 182a formed between the control cavities 140a arranged horizontally, adjacent, or between the control cavities 140a and the fuel pipes 135a.
[0093] As shown in Figures 12B and 12E, control cavities 140a may include the same moderator as reflective zone 95, due to the fact that the moderator may be free to move between reflective zone 95 and control cavities 140a through spans 162a and 182a. As the moderator confined in the control cavity 140a is heated by neutrons and gamma radiation emitted from the fuel tubes 135a, and heat is conducted from the fuel tubes 135a, part or all of the moderator in the control cavity 140a can be heated to a gaseous state in a gaseous zone 185a. Part or all of the moderator in control cavity 140a may also be in a liquid state in a liquid zone 190a. The gas zone 185a and liquid zone 190a can be separated by a boundary 195a. The size of the gas zone 185a and liquid zone 190a can vary between different control wells 140a and within each control well 140a at different times during operation of the reactor 15.
[0094] Thus, the location of limit 195a can vary between control cavities 140a. For example, a given control cavity 140a can have either a gas zone 185a or a liquid zone 190a, substantially only a gas zone 185a, or substantially only a liquid zone 190a.
[0095] The heat given through neutrons, gamma radiation and / or conduction from fuel tubes 135a can cause the liquid moderator of liquid zone 190a to be kept at a temperature very close to the boiling point of the moderator . For example, the moderator of the liquid zone 190a can be kept in a latent state. As the moderator in the liquid zone 190a boils slightly, part of the moderator may evaporate and rise to the gas zone 185a. The moderator in the liquid zone 190a can be cooled by mixing with the relatively cooler moderator that passes to the control cavity 140a through the small orifices 337a in the moderator refrigerant tube 335a. In addition, the moderator in the gas zone 185a may condense around the droplets of a relatively cooler, thinner moderator spray, which passes through the small orifices 337a in the moderator refrigerant tube 335a, or can condense and drip back into the liquid zone 190a along the internal surfaces of the control cavity 140a and / or an external surface of the moderator refrigerant tube 335a. The size of gaseous zone 185a can therefore remain substantially constant, and limit 195a can remain relatively stationary, with the amount of heat imparted through neutrons and gamma radiation from fuel tubes 135a and the amount of heat removed by the subsystem reactor refrigerant 25 are substantially the same. As further described below, the size of the gas zone 185a and a position of the boundary 195a may vary slightly over short periods of time (for example, over a period of days) based on the samarium and xenon load of the fuel, and may vary significantly over long periods of time (for example, over a period of years), based, for example, on the aging (or depletion) of the fuel. The size of the gas zone 185a and the position of the limit 195a can vary slightly during and briefly after periods of change in the cooling rate through the reactor refrigerant subsystem 25.
[0096] As shown in Figure 12E, control cavities 140a can be cooled by moving the cooler moderator through the moderator refrigerant tube 335a and to control cavities 140a through one or more orifices 337a located on the sides of the 335a moderator refrigerant tube. The orifices 337a can be of any size adapted for the moderator's movement such as, for example, the orifices which are small in size. A substantially equal volume of more moderator can then move from the control cavity 140a to the reflective zone 95 through the gap 162a in the lower portion of the control cavity 140a.
[0097] As shown in Figures 12C and 12D, the lower part of the reflective zone 95 can be cooled by moving the cooler moderator from the moderator refrigerant tube 335a through one or more small orifices 338a located in a lid in a lower end of the moderator refrigerant tube 335a.
[0098] Figure 12G provides a perspective view of the arrangement of the control cavities 140a of the reactor core 100a. It is contemplated that the various elements disclosed in reactors 100, 100 ', 100a and / or 100b can be used in combination with each other.
[0099] Figures 12H to 12M represent a fourth modality with an array of vertical fuel tubes and cooled hot moderator by pumping the hot moderator from the water mirror 105 and the control cavity matrix 130b, cooling them , and pumping the cooler moderator back to the control cavity matrix 130b and the water mirror 105. In this embodiment, each control cavity assembly can be an annular stack of control cavities surrounding a single fuel tube vertical. As illustrated in Figure 12H, this embodiment can include a reactor core 100b.
[00100] Reactor core 100b may include a fuel assembly 125b, which is similar to fuel assembly 125, and a control cavity matrix 130b. The control cavities 140b of the control cavity matrix 130b may contain a moderator and / or moderator vapor pocket adjacent to the fuel assembly 125b.
[00101] Fuel assembly 125b can be any type of nuclear fuel suitable for use in a nuclear reaction. For example, as shown in Figure 12J, fuel assembly 125b can include bundles of fuel rods 127b that are arranged in a plurality of fuel tubes 135b. For example, fuel assembly 125b may include an array of dozens to hundreds of fuel tubes 135b. For example, fuel assembly 125b may include between approximately 19 and approximately 500 fuel tubes 135b that are approximately three inches to approximately 18 inches in diameter. Each fuel tube 135b may include a single fuel bundle of relatively long fuel rods 127b or any suitable number of fuel bundles such as, for example, 12 fuel bundles of relatively short fuel rods 127b. Each fuel bundle can include any suitable number of fuel rods 127b between approximately 19 and approximately 1,231 fuel rods such as, for example, 37 fuel rods. The fuel assembly 125b can include any fuel suitable for a nuclear reaction such as, for example, natural uranium, enriched uranium, plutonium, or thorium, individually or in various mixtures. Fuel rods 127b can be molded metal fuel, or fuel rods or fuel oxide pellets in a liner tube (for example, a zirconium alloy tube). For example, fuel assembly 125b may include a mixed uranium / plutonium fuel or a mixed light water reactor fuel and thorium fuel. Fuel tubes 135b may also contain fuel in other forms than rods such as, for example, spheres or pebbles. The fuel tubes 135b may also contain a molten salt in which the metal ion of the salt is an ion of the fuel, and the molten salt functions as both the fuel and the refrigerant.
[00102] Each fuel tube 135b can contain the primary refrigerant in addition to the fuel. The primary refrigerant can include any material in a suitable fluid state such as, for example, heavy water, light water, suitable liquid metal (for example, lead or sodium), suitable molten salts, suitable organic fluids and / or a suitable gas ( for example, helium).
[00103] Fuel assembly 125b may include fuel tubes 135b that are arranged vertically (for example, as shown in Figure 2). The fuel assembly 125b can include fuel pipes 135b arranged in any suitable configuration such as, for example, a right angle matrix as shown in Figures 4 and 5. The fuel assembly 125b can also include, for example, the fuel pipes. fuel 135b which are arranged in a hexagonal matrix as shown in Figure 6. Fuel tubes 135b can be, for example, substantially and vertically arranged.
[00104] With reference again to Figures 12H to 12M, the control cavity matrix 130b may include a three-dimensional matrix of control cavities 140b. For example, the three-dimensional array of control cavities 140b can serve as a housing for compartmentalizing and / or confining moderator pockets adjacent to fuel tubes 135b of fuel assembly 125b. As shown in Figures 12H to 12M, the plurality of control cavities 140b can be arranged in vertical stacks with the stacks arranged horizontally in relation to each other, in addition to being stacked vertically. The control cavities 140b can be scaled vertically inside the control cavity matrix 130b. Control cavities 140b can be arranged in any configuration suitable for confining moderator pockets and / or moderator vapor adjacent to fuel tubes 135b.
[00105] As shown in Figures 12J to 12M, each control cavity 140b may include a moderator coolant inflow tube 335b, a moderator flow tube 337b, an inclined upper member 155b and side members 160b and 162b. As shown in Figure 12L, side member 160b can be, for example, approximately circular or approximately hexagonal for a hexagonal fuel tube arrangement, or approximately square for a square fuel tube arrangement. The upper limbs 155b can be joined without gaps in relation to the side members 160b and 162b, moderator refrigerant inflow tube 335b, and / or moderator drain tube 337b to confine a moderator pocket and / or moderator vapor adjacent to the 135b fuel lines. The moderator may be free to move between the control cavity 140b and the moderator refrigerant drain pipe 337b through an orifice 338b located in the lower portion of each control cavity 140b.
[00106] The upper limbs 155b, side members 160b and 162b and tubes 335b and 337b can be formed from any structural materials suitable to direct the moderator's movement or confine the moderator such as, for example, zirconium alloy. Upper members 155b, side members 160b and 162b and tubes 335b and 337b can be attached to each other by any suitable technique, such as, for example, welding. Upper members 155b, side members 160b and 162b and tubes 335b and 337b can also be integrally formed with each other. The upper members 155b, side members 160b and 162b and tubes 335b and 337b can be attached to form, for example, a cavity that has a closed upper portion and an open bottom portion. In this way, the upper limb 155b, side members 160b and 162b and tubes 335b and 337b can substantially prevent movement of the moderator in and out of an upper portion of control cavity 140b, while allowing the moderator to move inward. and out of a lower portion of the control cavity 140b. The upper portion of the control cavity 140b may include upper member 155b, upper portions of side members 160b and 162b and portions of tubes 335b and 337b. The lower portion of the control cavity 140b may include lower portions of side members 160b and 162b, and portions of tubes 335b and 337b. The orifice 338b and the moderator flow tube 337b can allow the moderator to move between the reflective zone 95 and the control cavities 140b. The moderator coolant inflow tube 335b can be sealed at its top end (for example, in a higher control cavity 140b associated with a given fuel tube 135b, as shown in Figure 12K). A span 180b can be arranged between control cavities 140b and fuel tubes 135b and can be filled with an inert gas or other suitable material and can be closed in a top and / or bottom portion to contain such material or to reduce circulation convection.
[00107] As shown in Figures 121 and 12L, control cavities 140b can include substantially the same moderator as reflective zone 95, because the moderator can move between reflective zone 95 and control cavities 140b through the drainpipe of moderator 337b and orifice 338b. As the moderator confined in the control cavity 140b is heated by neutrons and gamma radiation emitted from the fuel tubes 135b and by the thermal conduction of the fuel tube 135b, part or all of the moderator in the control cavity 140b can be heated to a gaseous state in a gas zone 185b. Part or all of the moderator in control cavity 140b may also be in a liquid state in a liquid zone 190b. A gas zone 185b and liquid zone 190b can be separated by a boundary 195b. The size of gas zone 185b and liquid zone 190b can vary between different control wells 140b. Thus, the location of boundary 195b can vary between control cavities 140b. For example, a given control cavity 140b may have both a gas zone 185b and a liquid zone 190b, substantially only a gas zone 185b, or substantially only a liquid zone 190b.
[00108] Heat conferred through neutrons, gamma radiation, and / or thermal conduction from fuel tubes 135b can cause the liquid moderator of the liquid zone 190b to be kept at a temperature very close to the boiling point of the moderator. For example, the moderator of the liquid zone 190b can be kept in a latent state. As the moderator in the liquid zone 190b begins to boil, part of the moderator may evaporate and rise to the gas zone 185b. In addition, the moderator in the gas zone 185b that is close to the moderator coolant inflow tube 335b or has a cold moderator sprayed at the same time from the moderator coolant inflow tube 335b through the holes 336b may condense and drip from back to the liquid zone 190b of the control cavity 140b. The holes 336b can be of any size suitable for the moderator's movement such as, for example, holes that are small in size. The size of gaseous zone 185b can therefore remain substantially constant and limit 195b can remain relatively stationary when the amount of heat imparted to each control cavity 140b by fuel tubes 135b (for example, by heat transfer, decreased neutron velocity and / or gamma radiation) and the amount of heat removed by the cooler moderator inflow is substantially equal. As further described below, the size of gas zone 185b and the position of boundary 195b may vary slightly over short periods of time (for example, over a period of hours or days) based on the fuel's xenon and samarium load, and can vary significantly over long periods of time (for example, over a period of years), based on, for example, the age (or depletion) of the fuel. The size of the gas zone 185b and the position of the limit 195b may vary slightly during and shortly after periods of change in the cooling rate by the reactor refrigerant subsystem 25.
[00109] As shown in Figure 12J, control cavities 140b can be cooled by the movement of the cooler moderator through the moderator coolant inflow tube 335b and into the control cavities 140b through holes 336b on the sides of the tube of 335b moderator refrigerant inflow. A substantially equal volume of warmer moderator can move out of control cavity 140b into reflective zone 95 and into reactor refrigerant subsystem 25 through orifice 338b and moderator flow pipe 337.
[00110] As shown in Figures 121, 12J and 12K, the lower portion of the reflective zone 95 can be cooled by flow from the cooler moderator from the moderator coolant inflow tube 335b through holes 336b in the lower portion of the coolant tube. inflow of moderator refrigerant 335b, the excess moderator flowing to the moderator refrigerant subsystem 315 (described below) through the moderator refrigerant drain pipe 337b.
[00111] As shown in Figures 121, 12J and 12K, the upper portion of the reflective zone 95 and the control cavity matrix 130b can be cooled by evaporation occurring at limit 115. During evaporation, excess steam moderator can move into the moderator refrigerant subsystem 315 (described below) through a transfer tube 323b.
[00112] As shown in Figure 12N, a tank 377b containing non-pressurized water (H2O) can include a plurality of moderator heat exchange tubes 390b that are fluidly connected to a moderator refrigerant tube 327b. The moderator heat exchange tubes 390b can extend through the non-pressurized water (H2O) contained in the tank 377b and can be connected fluidly through a passage 355b with a moderator cooling pump 350b. A passage 322b can fluidly connect the moderator cooling pump 350b to the moderator coolant inflow tube 335b which is arranged in the control cavity matrix 130b. A steam pressure control valve 380b may allow part of the steam moderator to pass from the steam transfer tube 323b to a plurality of steam heat exchange tubes 385b when a pressure in the steam transfer tube 323b is greater than a desired pressure. The moderator steam in the steam heat exchange tubes 385b can condense on the inner walls of the steam heat exchange tubes 385b or can escape out of a bottom portion of the steam heat exchange tubes 385b and condense to the cold moderator disposed in the moderator 390b heat exchange tube.
[00113] Tank 377b can be any suitable tank to be substantially filled with non-pressurized water (H2O) so that the temperature may not exceed the boiling point of water (H2O). In normal operation, the 377b tank can be cooled by any method suitable for just below the boiling point of water (H2O). In a situation where the power of the reactor 15 is interrupted, or another situation where the normal cooling operates abnormally, the tank 377b can be cooled by evaporation from the surface of the water (H20) disposed in the tank 377b.
[00114] As shown in Figure 13, the reactor refrigerant subsystem 25 can include a transfer subsystem 305, a fuel refrigerant subsystem 310 and a moderator refrigerant subsystem 315. Transfer subsystem 305 can transfer reactor refrigerant between the heat exchanger 20 and the reactor core 100, 100 ', 100a and / or 100b. The fuel refrigerant subsystem 310 can facilitate heat exchange from fuel tubes 135, 135 ', 135a and 135b, and the moderator refrigerant subsystem 315 can facilitate heat exchange from control cavities 140', 140a , 140b and reflective zone 95.
[00115] Reactor refrigerant subsystem reactor refrigerant 25 can be any suitable fluid material to facilitate heat exchange of reactor core 100, 100 ', 100a and / or 100b. For example, the reactor refrigerant can include D2O ("heavy water"), H2O ("light water"), molten metal or salt, or a gas. A similar refrigerant can be used for the fuel refrigerant subsystem 310 and moderator refrigerant subsystem 315, or a different refrigerant can be used for the fuel refrigerant subsystem 310 and the moderator refrigerant subsystem 315.
[00116] Transfer subsystem 305 can include a cold reactor refrigerant passage 320 and a hot reactor refrigerant passage 325. Passages 320 and 325 can be formed of any material suitable for transferring reactor refrigerant such as, for example, example, zirconium alloy and / or steel. The same passages 320 and passage 325 can transfer the reactor refrigerant to both the fuel refrigerant subsystem 310 and to the moderator refrigerant subsystem 315 (as, for example, in the first exemplary embodiment), or the separate passages 320 and 325 can be provided for fuel refrigerant subsystem 310 and passages 322a, 327a, 322b, 327b and similar passages in reactor core 100 '(not shown) for moderator refrigerant subsystem 315. The cold reactor refrigerant pass 320 can transfer the cold reactor refrigerant from heat exchanger 20 to the reactor 15. The cold reactor refrigerant can be in a liquid state and can be any suitable temperature to facilitate heat exchange from the reactor 15.
[00117] Referring back to Figure 2, for example, the cold reactor refrigerant passage 320 may pass through the openings of the containment structure 85 and into the reflective zone 95. The cold reactor refrigerant passage 320 can communicate with the passages of the fuel refrigerant subsystem 310 and moderator refrigerant subsystem 315 within the reflective zone 95 and can thereby supply the fuel refrigerant subsystem 310 and the moderator refrigerant subsystem 315 with refrigerant cold reactor for heat exchange. The hot reactor refrigerant passage 325 can be in fluid communication with the fuel refrigerant subsystem 310 and the moderator refrigerant subsystem 315 and can receive hot reactor refrigerant (for example, reactor refrigerant that has passed through the reactor core 100, 100 ', 100a and / or 100b in fuel tubes 135, 135', 135a and / or 135b, thereby facilitating the exchange of heat with the reactor core 100, 100 ', 100a and / or 100b) the fuel refrigerant subsystem 310 and the moderator refrigerant subsystem 315. The hot reactor refrigerant passage 325 can transfer the hot reactor refrigerant from the reactor 15 back to the heat exchanger 20.
[00118] As illustrated, for example, in Figure 3, the fuel refrigerant subsystem 310 can include a plurality of passages 330 that can be in fluid communication with the cold reactor passage 320 and hot reactor refrigerant passage 325 of the subsystem transfer 305. Cold reactor refrigerant can flow from cold reactor passage 320 to passages 330. Passages 330 can be arranged leading to and from fuel tubes 135, 135 ', 135a and / or 135b. The cold reactor refrigerant can pass through the passages 330, passing through the fuel pipes 135, 135 ', 135a and / or 135b to facilitate the heat exchange with the fuel pipes 135, 135', 135a and / or 135b. The cold reactor refrigerant can be heated by the fuel disposed in tubes 135, 135 ', 135a and / or 135b and can be transferred from fuel tubes 135, 135', 135a and 135b via passages 330. Passages 330 can then transferring the hot reactor refrigerant to the hot reactor refrigerant passage 325 of the transfer subsystem 305. The hot reactor refrigerant can be in a substantial and completely liquid state, it can be in a partially liquid state and a partially gaseous state, or it can be in a substantial and completely gaseous state.
[00119] As illustrated, for example, in Figure 2, the moderator refrigerant subsystem 315 can include a plurality of passages 335 that can be in fluid communication with the cold reactor cooler passage 320 and hot reactor coolant passage 325 from transfer subsystem 305. Cold reactor refrigerant can flow from cold reactor refrigerant passage 320 to passages 335 and 330. Cold reactor refrigerant can be in a liquid state. Passages 335 can be arranged inside control cavities 140. The cold reactor refrigerant can pass through passages 335, thereby passing through control cavities 140 to facilitate heat exchange with control cavities 140. O cold reactor refrigerant can be heated by the moderator confined within control cavities 140 in heated reactor refrigerant and can be transferred from control cavities 140 via passages 335. Similar to the heat exchange performed through passages 335 in the revealed control cavities , passages 330 can transfer cold reactor refrigerant from the cold reactor refrigerant passage 320 through the water mirror 105. It is also contemplated that the cold reactor refrigerant can be heated by the water mirror moderator 105 in heated reactor refrigerant. Passages 335 and 330 can then transfer the heated reactor refrigerant to a lower portion of the fuel pipes 135, through the fuel pipes 135 (where it is heated by the fuel to become the hot reactor refrigerant) and then to the passage of hot reactor refrigerant 325 from transfer subsystem 305. The hot reactor refrigerant can be in a substantial and completely liquid state, it can be in a partially liquid state and a partially gaseous state.
[00120] Figure 14 illustrates an exemplary detailed illustration of passage 335 as it passes through control cavities 140 to facilitate heat exchange from control cavities 140. Passage 335 can be connected to cool reactor refrigerant passage 320 and / or to the hot reactor refrigerant passage 325 of transfer subsystem 305 directly or via an intermediate passage 345. Passage 335 may include an inlet member 350, an inner member 355, an outer member 360 and a member outlet 3 65. Inlet member 350 can fluidly connect intermediate passage 345 with inner member 355. Inner member 355 can be arranged within an interior of outer member 360. For example, inner member 355 and external member 360 can be an arrangement of concentric tubes. Outlet member 365 can fluidly connect external member 360 with intermediate passage 345. Inlet member 350 can pass through an opening in a wall of outlet member 365 and may be partially arranged within outlet member 365 The inner member 355 may have an openable end portion 370. A plurality of openings 375 can be formed through an inner member wall 355. Openings 375 can increase in size and a space between openings 375 can decrease in a directional movement towards end portion 370 of inner member 355 The reactor refrigerant can flow from the inlet member 350 and through a channel 380 of the inner member 355. Some reactor refrigerant can pass through the openings 375 and into a channel 385, before reaching the open end portion. 370 of the inner member 355. A size and frequency of the openings 375 can increase, in a directional movement towards the end portion 370 and a quantity of reactor refrigerant mixture between channels 380 and 385 can increase in a directional movement towards end portion 370. Channel 385 can be formed between inner member 355 and outer member 360 and can be a ring shaped channel. After passing through openings 375 and / or open end portion 370, reactor refrigerant can flow through channel 385 and into intermediate passage 345 through outlet member 365. The reactor refrigerant disposed in channel 385 can be heated by the thermal conduction of the hottest moderator in the control cavity 140 through the wall of the external member 360. By allowing a relatively cooler flow of coolant from channel 380 to channel 385 through openings 375, the temperature of the refrigerant in channel 385 can be relatively constant along its length. The heat transfer fins (not shown) can be added to the inner and / or outer surfaces of the outer member 360 to facilitate heat transfer.
[00121] Referring back to Figure 13, pump subsystem 30 can include a cooling pump 390, an H2O pump 395 and an engine 400. The engine 400 can drive the cooling pump 390 and the H2O pump 395 .
[00122] Cooling pump 390 can be any suitable type of pump to pressurize the flow of reactor refrigerant in transfer subsystem 305. For example, cooling pump 390 can be a positive displacement pump such as a type pump rotary pump, a reciprocating pump, or a linear pump. In addition, for example, the cooling pump 390 can be a steam pump, a boost pump, a hydraulic ram pump, or a centrifugal pump. Cooling pump 390 can pressurize a stream of reactor refrigerant in the cold reactor refrigerant passage 320 from heat exchanger 20 to reactor 15 and into the hot reactor refrigerant passage 325 from reactor 15 back to the heat exchanger 20. The cooling pump 390 can pressurize the same reactor refrigerant in the transfer subsystem 305 for both the fuel refrigerant subsystem 310 and the moderator refrigerant subsystem 315, or one or more cooling pumps 390 it can separately pressurize the reactor refrigerant for the fuel refrigerant subsystem 310 and cool the moderator for the moderator refrigerant subsystem 315.
[00123] The H2O 395 pump can be of a type similar to the cooling pump 390 and can pressurize a flow of water (H2O) and steam (H2O) in the turbine steam subsystem 65. The H2O 395 pump can pressurize a hot steam flow (H2O) in passage 70 from heat exchanger 20 to turbine 45, an excess or dead steam flow (H2O) in passage 75 from turbine 45 to turbine cooling subsystem 60 and a flow of water (H2O) in passage 80 from turbine cooling subsystem 60 to heat exchanger 20.
[00124] Motor 400 can be any suitable type of motor to drive cooling pump 390 and H2O pump 395 such as, for example, a variable displacement or fixed motor, a hydraulic motor of the type of folded geometry axis, a linear hydraulic motor, hydraulic cylinder or electric motor. Motor 400 can drive cooling pump 390 and H2O pump 395 in any suitable manner such as, for example, by means of one or more mechanical rods 405. For example, motor 400 can drive both cooling pump 390 as for the H2O 395 pump through a single mechanical rod 405. The mechanical rod 405 may include an engine flywheel that operates to mitigate rapid flow changes as the engine 400 drives the cooling pump 390 and the H2O pump 395 Motor 400 can also drive cooling pump 390 and H2O pump 395 separately. It is also contemplated that the engine 400 can drive the pump 390 and the H2O pump 395 by other suitable techniques such as, for example, hydraulically. The engine 400 can be configured to drive both the cooling pump 390 and the H2O pump 395 at an optimized level when the nuclear reactor system 5 is operating at full power. The engine 400 can start both the cooling pump 390 and the H2O pump 395 when engine 400 is deactivated or stops operating and both the cooling pump 390 and the H2O 395 pump can also deactivate simultaneously. It is also contemplated that each pump may have a separate motor.
[00125] As shown in Figures 16 to 18, the auxiliary refrigerant subsystem 35 may include a convection loop subsystem 410 and an auxiliary heat exchange subsystem 415. The convection loop subsystem 410 and auxiliary heat exchange subsystem 415 can provide auxiliary systems to facilitate heat exchange from reactor 15.
[00126] As shown in Figure 16, the convection loop subsystem 410 may include a junction 425, a passage 430, a passage 435, a plurality of passages 440 and 445, a converging portion 450, a junction 455, a valve 460 and valve 465. Junction 425, passage 430, passage 435, the plurality of passages 440 and 445, the converging portion 450 and junction 455 can be formed from any material suitable for transferring reactor refrigerant and can be in fluid communication to provide an auxiliary reactor refrigerant path. Junction 425 can be configured to maintain pressure A at an inlet of passageway 430. A portion of reactor refrigerant flowing through the hot reactor refrigerant passage 325 can flow into passageway 430 at junction 425. Passage 430 can direct the flow of reactor refrigerant down below the limit 115 of the reflective zone 95, thereby orienting the flow below a top surface of the water mirror 105. The reactor refrigerant can flow from passage 430, upwards through passage 435 and then towards containment structure 85 and pressure vessel 90 through the plurality of passages 440. The plurality of passages 440 can be in fluid communication with the plurality of passages 445. The plurality of passages 440 and 445 can be sized to be smaller than the passages 430 and 435 and can be, for example, a plurality of small tubes. The plurality of passages 445 can be arranged adjacent to a surface of the pressure vessel 90 so as to have a good heat exchange with the pressure vessel 90. For example, the plurality of passages 445 can be welded to the pressure vessel 90. The plurality of passages 445 can transfer reactor refrigerant down along pressure vessel 90, to a position close to or below a bottom of the reactor core 100, 100 ', 100a and / or 100b.
[00127] The plurality of passages 445 can be connected fluidly with and converge in one or more converging portions 450, which can be larger than the plurality of passages 445. For example, several passages 445 can converge in each one of one plurality of larger converging portions 450. One or more converging portions 450 can fluidly connect to the cold reactor refrigerant passage 320 at junction 455. A junction 455 can be configured to maintain a pressure B at an outlet of one or more portions converging 450 so that when cooling pump 390 is providing a flow of refrigerant for full power operation, pressure A in passage 430 can balance pressure B so that relatively little refrigerant passes between junction 425 and junction 455 through passages 430, 435, 440, 445 and converging portion 450. When pump 390 is not operating and reactor core 100 is still producing heat, the hot refrigerant in fuel tubes 135 can rise and flow into the passage 430 because the passage 325 can be substantially blocked by the pump 390. The hot refrigerant can continue through the passages 435 and 440 to the plurality of passages 445. In the passages 445, the refrigerant can transfer heat to the reflective zone 95 and pressure vessel 90 and can become more dense as it cools. That relatively denser moderator can fall through passage 445 and junction 455 and move the relatively hotter moderator in fuel tubes 135, thereby creating a convection circuit that can cool fuel tubes 135.
[00128] Valves 460 and 465 can be provided to isolate a flow of reactor refrigerant within the convection loop subsystem 410 in the event of a flow interruption and / or loss of refrigerant, external to reactor 15, from the refrigerant subsystem of reactor 25. Valve 460 can be arranged in the cold reactor refrigerant passage 320 and can be any suitable valve to substantially block the flow of reactor refrigerant out of reactor 15. For example, valve 460 can be a one-way valve or a reverse block valve that can allow the reactor refrigerant to flow into the reactor 15 through the cold reactor refrigerant passage 320, but can substantially block a reactor refrigerant flow out of the reactor 15 via the cold reactor refrigerant passage 320. For example, valve 460 may be arranged in the cold reactor refrigerant passage 320 in a portion on or near a surface outer surface of the containment structure 85. The valve 465 can be arranged in the hot reactor refrigerant passage 325 and can be any suitable valve to substantially block the reactor refrigerant flow from the reactor 15 when the reactor refrigerant quantity is less than than a limit quantity. For example, valve 4 65 can be a floating valve that can allow reactor refrigerant to flow out of reactor 15 through the hot reactor refrigerant passage 325 when the reactor refrigerant level is greater than the limit quantity , but it can substantially block a reactor refrigerant flow from the reactor 15 via the hot reactor refrigerant passage 325 when the reactor refrigerant level is less than the limit quantity. For example, valve 465 can substantially block reactor refrigerant flow from reactor 15 when the hot reactor refrigerant passage 325 is less than half full of reactor refrigerant. The valve 465 can be arranged in the cold reactor refrigerant passage 325 in a portion on or near an external surface of the containment structure 85.
[00129] As shown in Figures 17 and 18, the auxiliary heat exchange subsystem 415 can include one or more heat exchange members 470, one or more heat exchange members 475 and one or more heat exchange members 480 Heat exchange member 470, heat exchange member 475 and heat exchange member 480 can facilitate the exchange of heat for heat produced by reactor core 100, 100 ', 100a, or 100b for a distant location of reactor 15.
[00130] The heat exchange member 470 may be an elongated element for housing a material. The heat exchange member can be arranged in the containment structure 85 (for example, molded into a wall of the containment structure 85) and can be arranged close to the pressure vessel 90 or in contact with an external surface of the pressure vessel 90. The heat exchange member 470 can be arranged radially in the containment structure 85, so that one end of the heat exchange member 470 can be adjacent to or in contact with the pressure vessel 90 and the other end of the member heat exchanger 470 may be close to an external portion of the containment structure 85. For example, the heat exchanger member 470 may be an elongated cavity housing a material in a changing state. For example, the heat exchange member 470 may include a cavity that houses a metal alloy. For example, the heat exchange member 470 may be a steel tube that is filled with a metal alloy. The changeable state metal alloy can be a material that has a melting point that is slightly higher than a normal operating temperature of the reflector zone moderator 95. For example, the heat exchange member 470 may be a steel tube hollow that is substantial and completely filled with lead, tin and / or any other material with a suitable melting point. If the temperature of the moderator within the reflective zone 95 exceeds its normal operating temperature, the changing material housed within the heat exchange member 470 can be heated from a solid to a liquid state. For example, the heat exchange member 470 may include lead as a material in change of state, which can be melted into molten lead when the moderator within the reflective zone 95 exceeds its normal operating temperature. When changing material changes state (for example, when lead melts), the conductivity properties of changing material can improve. Therefore, the changing material of the heat exchange member 470 can effectively transfer heat (for example, by convection) away from pressure vessel 90 and towards an exterior of containment structure 85 (which can having low thermal conductivity), as the changing material melts. It is also contemplated that the changing state material housed within the heat exchange member 470 can be in a liquid state at normal moderator operating temperatures and can be heated to a gaseous state when the moderator temperature exceeds a temperature of normal operation.
[00131] The heat exchanger member 475 can also be an elongated cavity that houses a changing state material, similar to the heat exchange member 470. The changing state material of the heat exchange member 475 can be a material with a lower boiling and / or melting point than the changing state material of the heat exchange member 470. For example, the changing state material can be a material in a liquid state and can have a boiling point which is less than the temperature at which the heat exchange member 47 0 undergoes a change of state (for example, the melting point of lead or any other material in suitable change of state of the heat exchange member 470 ). For example, the heat exchange member 475 can be a steel tube that is filled with water (H2O) or any other suitable material in a liquid state. The heat exchange member 475 can be arranged substantially vertically within the retaining structure 85 (for example, molded into a retaining structure wall 85). As shown in Figures 17 and 18, heat exchange member 475 may be in contact with or disposed near an end portion of one or more heat exchange members 470 and may be disposed near an external surface of the heat exchanger structure. containment 85. Material changing the state of heat exchange member 475 may be heated by heat transferred from heat exchange member 470 and may undergo a change of state. For example, the heat transferred from an end portion of the heat exchange member 470 to the heat exchange member 475 can cause the changing material to change state (for example, it can cause water housed in the steel tube boil). It is also contemplated that the material in changing state of the heat exchanger member 475 may be in a liquid state at normal moderator operating temperatures and can be heated to a liquid state when the moderator temperature exceeds a normal operating temperature .
[00132] Heat exchange member 480 may be similar to heat exchange member 475 and may be in fluid communication with heat exchange member 475. The material changing state of heat exchange member 475 may then flow from heat exchange member 475 into heat exchange member 480. Heat exchange member 480 may be arranged at a small angle to a substantially horizontal plane. The heat exchange member 480 may be arranged in a small degree such as, for example, 1 in 20 (rise over run formula) or 1 in 50 (rise over run formula). As shown in Figure 18, heat exchange members 480 can spread from reactor 15, thereby transferring heat away from reactor 15. Heat exchange members 480 can be arranged under a surface of the earth thereby transferring heat from reactor 15 under any suitable amount of the earth's surface. For example, heat exchange members 480 may be arranged under a large field and / or parking, thereby utilizing the large thermal capacity of the soil to absorb heat and use the earth's surface to dissipate heat. Because the heat exchange member 480 can be at a slight slope, the changing material housed within the heat exchange member 480 can be cooled over a given distance from the reactor 15 to the previous state. For example, the heat exchanger member 475 can include water that can be heated in steam (H2O) and transferred into the heat exchange member 480. At one outer end, the heat exchange member 480 can terminate in a small tank or water tank so that the heat exchange members 475 and 480 are substantially always filled with water. The heat exchange member 480 can be a corrugated tube configured to increase a contact area of the tube (for example, to increase the contact area per unit distance along the ground) and also to increase the contact area of any vapor ( H2O) in the tube with the inner tube surface. Since the steam (H2O) that flows out along the top surface of the water (H2O) in the tube fills the top portion of each corrugation in the tube before any steam (H2O) can additionally run out of the tube, the corrugation increases the water surface area (H2O) in the tube that is in contact with the steam (H2O). After a given distance, sufficient heat can be dissipated so that the vapor (H2O) condenses into water (H2O).
[00133] As shown in Figure 19, an auxiliary reactor shutdown subsystem 420 can include a pressurized reservoir 485, one or more passages 490, a drain passage 495 and a pump 500. The pressurized reservoir 485 can supply pressurized water (H2O ) into the passage 490. The pump 500 can pressurize the water (H2O) in the drain passage 495.
[00134] The pressurized reservoir 485 can be any container suitable for storing pressurized liquid such as, for example, a pressurized steel vessel. Any suitable neutron-absorbing material can be stored in the pressurized reservoir 485 such as, for example, water (H2O). In addition, borated water (H2O), which has absorbed boron mixed in water (H2O), can be stored in the pressurized reservoir 485. The pressurized reservoir 485 can be arranged on an external side of the containment structure 85 and can include a 487 valve which can be opened and closed to flow to allow or selectively block the flow of pressurized material from pressurized reservoir 485 in one or more passages 490.
[00135] Passage 490 can be any suitable passage for transferring pressurized material. The passage 490 can be fluidly connected to the pressurized reservoir 485 and can transfer the pressurized material from the pressurized reservoir 485 through an opening of the containment structure 85 and can be divided into one or more U-shaped tubes that pass through the area core into reflective zone 95 below reactor core 100, 100 ', 100a, or 100b and then back up through reactor core 100, 100', 100a, or 100b. Passage 490 can transfer the pressurized material through the reflecting zone 95 and reactor core 100, 100 ', 100a, or 100b in any suitable manner. For example, as shown in Figure 19, passage 490 can enter an upper portion of the water mirror 105 and form a substantially U-shaped configuration. Passage 490 can be formed in any suitable configuration within reflective zone 95. When valve 487 is blocking the flow of pressurized material from pressurized reservoir 485 into passage 490, passage 490 can now be filled with steam (H2O). When a quick shutdown of the reactor is desired (eg SCRAM), valve 487 is opened and pressurized neutron absorbing material such as, for example, borated water (H2O) fills passage 490, pressurized neutron absorbing material can increasingly pressurize the steam (H2O) that was previously disposed in passage 490. Therefore, the steam (H2O) previously disposed in passage 490 can be increasingly pressurized at an end portion 505 of each or more passages 490, gradually slowing down and stopping additional flow.
[00136] The drain passage 495 can be arranged in a lower portion of the water mirror 105 and can fluidly connect any portion (for example, a lower portion) of the passage 490 with the pressurized reservoir 485. The pump 500 can be arranged in the drain passage 495 and can pressurize the neutron absorbing material to flow from the lower portion of the passage 490 back to the pressurized reservoir 485 when reactor 15 is to be restarted. Pump 500 can also pressurize the disposed neutron absorbing material in the pressurized reservoir 485. The pump 500 can thereby pump the neutron absorbing material such as, for example, borated water (H2O), from the passage 490 back to the pressurized reservoir 485.
[00137] As shown in Figure 20, reactor control subsystem 40 can include a control subsystem 510, a load monitoring subsystem 515, a bypass subsystem 520, a moderator stabilization subsystem 525, a stabilization subsystem reactor refrigerant 530 and a differential flow subsystem 535. Control subsystem 510, load tracking subsystem 515, bypass subsystem 520, moderator stabilization subsystem 525, reactor refrigerant stabilization subsystem 530 and subsystem differential flow 535 can control and / or stabilize an operation of the nuclear reactor system 5.
[00138] The control subsystem 510 can include a controller 540 which can be any type of programmable logic controller suitable for automating machine processes. Controller 540 can be connected to the components of the nuclear reactor system 5 by means of electrical lines (not shown) and can control an operation of any suitable component of the nuclear reactor system 5 by means of the electrical lines. For example, controller 540 can be electrically connected and control components of the power generation subsystem 10, reactor 15, heat exchanger 20, reactor refrigerant subsystem 25, pump subsystem 30, auxiliary refrigerant subsystem 35 and / or reactor control subsystem 40. The control subsystem 510 may also include intake and / or emission components that are in electrical communication with the 540 controller such as, for example, displays, monitors, keyboards and other devices for use by nuclear reactor system 5. The control subsystem 510 can also include sensors that are arranged in the various passages and components of the nuclear reactor system 5. The sensors can measure any suitable parameter such as, for example, a temperature and / or pressure of , for example, H2O or reactor refrigerant. The sensors can be electrically connected to the 540 controller and can input detected data to the 540 controller for use in controlling the nuclear reactor system 5.
[00139] The load monitoring subsystem 515 can include gates 545 and 550, passages 555, 560, 565, 580 and 590, a condenser 570, a valve 575, a heat exchanger 585 and a junction 595, which can be any elements suitable for transferring steam (H2O) and water (H2O).
[00140] Port 545 can be arranged in passage 70 and can selectively allow flow from passage 70 into passage 555. Port 545 can be selectively moved from a closed position that substantially blocks the flow of steam (H2O ) from passage 70 to the interior of passage 555, an open position that substantially allows the complete flow of passage 70 into interior of passage 555 and a partially open position positioned at any desired interval between the closed position and the open position and allowing, thereby, a partial flow, proportional to the amount by which the port 545 is opened, of steam (H2O) from passage 70 into passage 555. Port 545 can thereby selectively reduce a flow of steam ( H2O) through passage 70 by diverting steam (H2O) through passage 555.
[00141] Port 550 can be arranged in passage 555 and can selectively allow flow from passage 555 into passage 560 if similar to the operation of port 545. Port 550 can therefore selectively lock, partially allow, or completely allow the flow of steam (H2O) from passage 555 into passage 560. Passage 560 can bypass turbine 45 and transfer steam (H2O) directly to turbine cooling subsystem 60. Therefore , port 550 can be operated to selectively allow steam (H2O) to be transferred directly to the 60 in turbine cooling subsystem in certain situations such as, for example, when a quick shutdown of turbine 45 is desired.
[00142] Passage 555 may be in fluid communication with passage 565. Passage 565 may transfer steam (H2O) from passage 555 to condenser 570. Passage 565 may pass through an exterior of heat exchanger 20, in instead of passing through an interior of the heat exchanger 20.
[00143] Condenser 570 may be disposed in contact with or adjacent to the passage of cold reactor refrigerant 320. Condenser 570 may be any condenser suitable for condensing steam (H2O) into water (H2O). Valve 575 can be arranged on condenser 570 at any suitable location such as, for example, on a bottom portion of condenser 570. Valve 575 can be any valve suitable for allowing water (H2O) to flow out of condenser 570 while substantially blocks a flow of steam (H2O) out of condenser 570. For example, valve 575 can be a floating valve. The condenser 570 and valve 575 can serve as a pressure reduction system, reducing the high vapor pressure (H2O) in passage 565 to a relatively low pressure of water (H2O) in passage 580.
[00144] Passage 580 can be in fluid communication with condenser 570. Passage 580 can transfer water (H2O) from condenser 570 to heat exchanger 585. Passage 580 can pass through an exterior of heat exchanger 20 instead of passing through an interior of the heat exchanger 20.
[00145] The heat exchanger 585 can be any suitable device to facilitate the exchange of heat from the water (H2O) transferred through the passage 580. The heat exchanger 585 can be arranged in or near a passage of the turbine steam subsystem 65 that transfers water (H2O) from an outlet of the H2O pump 395 to the heat exchanger 20. The heat exchanger 585 can cool a water temperature (H2O) to a temperature substantially the same as water (H2O) being transferred via passage 80 of the turbine steam subsystem 65. Passage 590 can transfer water (H2O) from heat exchanger 585 to passage 80 via junction 595. Water (H2O) transferred through passage 590 to the The interior of the passage 80 can have a temperature substantially the same as the water temperature (H2O) already flowing in the passage 80. The passage 80 can then transfer the water (H2O) to an inlet of the H2O pump 395 of the pump subsystem 30.
[00146] The bypass subsystem 520 may include a pump 600 and a passage 605. The passage 605 can fluidly connect the cold reactor refrigerant passage 320 and the hot reactor refrigerant passage 325 of the transfer subsystem 305. The pump 600 may be arranged at passage 605. Pump 600 may have a relatively small capacity such as, for example, between about 2% and about 20% of pump 390 capacity. Pump 600 may operate to pressurize the reactor refrigerant in passage 605 to pump reactor refrigerant from the hot reactor refrigerant passage 325 into the cold reactor refrigerant passage 320, thereby diverting heat exchanger 20 and pump 390. Pump 600 and passage 605 can allow relatively hot reactor refrigerant to flow through the hot reactor refrigerant passage 325 to bypass heat exchanger 20 and flow directly into the refrigeration passage cold reactor 320, thereby allowing the hot refrigerant to mix with the relatively cold refrigerant and raise the temperature of the refrigerant flowing in the cold reactor refrigerant passage 320. The bypass subsystem 520 can operate, for example, during an initial reactor refrigerant charge and / or shutdown of the nuclear reactor system 5. The bypass system 520 can also serve to adjust the effective flow ratios of pumps 390 and 395 (for example, pump subsystem 30 can be designed to provide the correct ratio of reactor refrigerant flow to the steam turbine flow at full power, but a slightly different ratio may be desirable in lower power operation).
[00147] The moderator stabilization subsystem 525 can include passages 610, 630, 640 and 650, a valve 615, a reservoir 625, a condenser 635 and a pump 645, which can be any suitable elements for transferring steam (JbO) and water (H2O).
[00148] Passage 610 can be a relatively large passage that can fluidly connect the steam area 110 of the reflective zone 95 with reservoir 625. Valve 615 may be arranged in passage 610. Valve 615 may be in a position closed, substantially blocking the steam flow moderator during normal operation. When valve 615 is opened, moderator steam can flow into reservoir 625 through passage 610. Reservoir 625 can be a low pressure reservoir that can be maintained at a pressure that is less than an area pressure of vapor 110 from reflective zone 95. Reservoir 625 can be a relatively cold and large storage area. For example, reservoir 625 can be cooled with a relatively large amount of water (H2O). For example, reservoir 625 can be cooled with water (H2O) from turbine vapor subsystem 65. Upon entry into reservoir 625 through passage 610, the moderator vapor can expand and condense on relatively cold surfaces on the inner walls of the reservoir 625. When valve 615 is opened, the rapid flow of moderator steam out of the steam area 110 of the reflecting zone 95 can reduce the pressure of the moderator vapor in the steam area 110 and the moderator pressure in the reflecting zone 95 , thus allowing the moderator to flow quickly out of control cavities 140, 140 ', 140a and / or 140b, thereby reducing the mass of the moderator in the control cavities, reducing the number of (slow) thermal neutrons available to cause fission , leading to a quick shutdown of the reactor 15.
[00149] Passage 630 can fluidly connect a passage 610 with capacitor 635. Passage 630 can be a relatively small passage. For example, passage 630 can be a tube that has a significantly smaller diameter than passage 610. Passage 630 can fluidly connect passage 610 to capacitor 635. Condenser 635 can be arranged in contact or adjacent to passage 80 , which can transfer relatively cold water (H2O), from the turbine steam subsystem 65. Condenser 635 can be any condenser suitable for condensing moderator vapor into moderator liquid. The moderator vapor transferred from the passage 610 through the passage 630 can be condensed in moderator liquid by the condenser 635. The passage 640 can fluidly connect the condenser 635 with the pump 645.
[00150] Pump 645 can selectively block a flow of condensate liquid from passage 640 into passage 650. Pump 645 can also selectively allow condensate liquid to flow into passage 650 and can operate to pressurize the condensed moderator liquid to flow through the passage 650. The passage 650 can transfer the condensed moderator liquid back into the reactor 15. For example, the passage 650 can fluidly connect a passage 650 with a upper portion of the reflective zone 95, for example, vapor area 110. Condensed moderator liquid transferred into vapor area 110 via passage 650 may cause additional moderator vapor in vapor area 110 to condense. The reflecting zone 95 can be heated by the neutrons escaping from the reactor core 100, 100 ', 100a and / or 100b and the moderator in the reflecting zone 95 can evaporate in moderator vapor in the steam area 110. The 645 pump can be operated to condense moderator steam in excess of the steam area 110 so as to maintain a stable pressure in the steam area 110 and reflective zone 95.
[00151] The reactor refrigerant stabilization subsystem 530 can include a reservoir 655, a heating element 660 and a passage 665. Reservoir 655 can be a pressurized storage tank that can store the reactor refrigerant. Reservoir 655 can be supplied with reactor refrigerant from reactor refrigerant subsystem 25 via passage 665 from hot reactor refrigerant passage 325. Reservoir 655 can include liquid reactor refrigerant in a bottom portion and refrigerant of gaseous reactor in an upper portion. The heating element 660 can selectively heat the reservoir 655 to maintain the reactor refrigerant stored inside the reservoir 655 at a desired temperature and / or pressure. The heating element 660 can be any device suitable for selectively heating the reservoir 655 such as, for example, an electric heater. The cold reactor refrigerant from the cold reactor refrigerant passage 320 can be selectively pumped into the 655 reservoir by a pump and supply line (not shown) from the cold reactor refrigerant passage 320. For example, the pump (not shown) may include an injector that sprays cold pressurized reactor refrigerant from the cold reactor refrigerant passage 320 into the top (steam) portion of the 655 reservoir. For example, the relatively cold reactor refrigerant can be sprinkled by the pump (not shown) inside reservoir 655 to condense a portion of the reactor refrigerant vapor in reservoir 655 to cause some of the reactor refrigerant vapor to condense and thereby reduce pressure in reservoir 655 and coolant passage of hot reactor 325.
[00152] As shown in Figures 15 and 20, the differential flow subsystem 535 may include a plurality of concentric passages 670 arranged in a portion 675 of the cold reactor refrigerant passage 320. Concentric passages 670 can replace portion 675 of the passage cold reactor refrigerant 320 and can be fluidly connected at both ends of portion 675 to the other portions of cold reactor refrigerant passage 320. Portion 675 can be an elevation portion of cold reactor refrigerant passage 320 that it may be arranged downstream of pump 390. Any suitable number of concentric passages 670, such as, for example, about ten concentric passages 670, may be arranged within the cold reactor refrigerant passage 320. Concentric passages 670 may, for example, be example, concentric steel tubes. The area between the concentric passages can increase, moving from the innermost passage 670 to the outermost passage 670. For example, an area A2 between the first and second concentric passages 670 can be twice as large as an area Al formed within the first concentric passage 670, an area A3 between the fourth and fifth concentric passages 670 can be five times larger than the area Al formed within the first concentric passage 67 0 and an area A4 between the ninth and tenth concentric passages 670 can be ten times greater than the area A1 formed within the first concentric passage 670. The portions of each area between each successive concentric passage 670 can be blocked at each end to maintain substantially the same flow rate in and out of each pass. concentric 670. Concentric passages 670 can therefore take a proportionately larger amount of time to transfer the same amount of flu gone in the external concentric passages in relation to the internal concentric passages and rapid temperature changes in the cold reactor refrigerant passage 320 can therefore be mitigated. INDUSTRIAL APPLICABILITY
[00153] In at least some exemplary embodiments of the disclosed nuclear reactor system, a reactor control method can be used having control cavities that enclose a moderator in a reactor core. In at least some exemplary modalities, the reactor moderator can be divided into three areas: a core area that can be arranged anywhere in the reactor less than about 0.3 meters (1 foot) from any part of a fuel source, a reflective zone that can include any moderator outside the core area but less than 0.91 or 1.22 meters (three or four feet) from any part of a fuel source and a moderator cluster that can include any moderator outside the core area and the reflecting zone. One function of the moderator in the core area is to slow down the high-speed neutrons emitted by the fission fuel to relatively low speeds where the neutrons are more likely to cause new fissions. A function of the moderator in the reflecting zone is to reflect the neutrons that escape from the core area back into the nucleus to decrease the number of neutrons that are lost from the reactor. The moderator in the moderator cluster may have little effect on the reactor (for example, the moderator can go to the moderator cluster when it is moved from the core moderator control cavities or it can come from the moderator cluster when the moderator returns to the core). In at least some exemplary embodiments, the revealed control cavities can enclose most moderators in the reactor core area and can be closed at the top, but allow free movement of the moderator between the bottom of the control cavity and the cluster areas moderator and reflector.
[00154] In at least some exemplary embodiments of the revealed nuclear reactor system, when the revealing nuclear reactor system is producing power at a steady rate, the fuel may be in a state of nuclear equilibrium and the control cavities may be in one thermal equilibrium state. The two equilibrium states are coupled by negative feedback so that any change in balance in one state causes a change in the balance of the other, which will act to contain the change in the first. The revealed control wells are provided with a moderator cooling system that cools the control wells at almost the same rate (or proportional to the volume of each control well if the control wells are not all of the same volume) by pumping moderator cold into the control cavities, mixing the heated moderator into the control cavity while an equal mass of the heated moderator passes out of the control cavity into the moderator and reflector pool areas, or passing fluid cooler through one or more tubes in the control cavity which then cools the control cavity by conduction. Heat can enter the control cavity by thermal conduction from the hot fuel tubes and by energy deposited in the moderator by fast neutrons and gamma radiation from the fuel. When more heat enters the control cavity than it leaves the control cavity, the moderator liquid in the cavity evaporates and rises in a vapor bubble at the top of the control cavity, while displacing the moderator liquid out of the bottom of the cavity. control and reduces the total mass of the moderator in the reactor core because the steam can be much less dense than the moderator liquid. When less heat enters the cavity than is extracted by the moderator cooling system, some of the steam in the vapor bubble condenses, reducing the size of the vapor bubble and extracting moderator liquid into the cavity of the reflecting and clogging zone. of moderator, thereby increasing the total mass of the moderator in the nucleus.
[00155] In at least some exemplary embodiments of the revealed nuclear reactor system, high-speed neutrons are emitted with each fission of an atom in the fuel. Most of these high-speed neutrons can escape from the fuel into the moderator (along with the qama radiation emitted by the fuel) and are slowed by collisions with the moderator. These slower neutrons diffuse from the moderator back into the fuel. Some of the slower neutrons can be absorbed by the fissile atoms in the fuel and cause new fission, some can be absorbed by the fertile atoms in the fuel (eg uranium 238, plutonium 240 and / or thorium 232, if present) and create new carbon atoms. fissile fuel and some can be absorbed into the fuel without causing fission or creating new fissile atoms or can diffuse back into the moderator. The reaction rate can be stable when, on average, exactly one neutron released by each fission causes a new fission. The probability that a neutron re-entering fuel from the moderator will cause a fission to decrease when the speed is relatively high and the probability that the neutron will create new fuel increases when the speed is relatively high. Neutrons that leave the moderator may have a higher average speed when there is less moderator mass in the cavity and may have a lower average speed when there is more moderator mass in the cavity. Consequently, as the vapor bubble increases in size (and therefore the moderator mass in the cavity decreases), the average speed of the neutrons entering the fuel increases, which increases the number of neutrons that are deflected effectively to cause new ones. fission and decreases the number of neutrons that are diverted to the production of new fissile fuel. This effect decreases the fission rate, reducing the energy transferred to the moderator, reducing the size of the vapor bubble and thereby providing negative feedback that maintains a stable vapor bubble size and maintains a fission rate that is stable and grossly proportional. at the moderator cooling rate.
[00156] Collectively, in at least some exemplary modalities of the revealed nuclear reactor system, the control cavities maintain the total power emission and proportional to the moderator cooling rate. The moderator cooling rate can be controlled by keeping the moderator refrigerant temperature relatively constant and varying the pumping rate to control the total cooling rate. Individually, each cavity can influence the fission rate of the fuel close to it, which causes the reaction rate to be almost the same at all points in the reactor instead of being higher in the center of the core and lower near the edges of the core . This can minimize hot spots in the fuel and suppress xenon waves, leading to higher desirable rates of heat extraction from the fuel.
[00157] During normal reactor operation in at least some exemplary embodiments of the revealed nuclear reactor system, heat is extracted from the fuel tubes by the primary refrigerant. When the reaction rate is increased, the rate of the primary cooling pump is also increased, so that the temperature of the fuel lines does not vary with the rate of reaction. Under abnormal conditions, the flow of the primary refrigerant may be insufficient and the fuel lines may become warmer. In such conditions, there may be more heat conduction from the fuel pipes into the control cavities, which can increase the evaporator rate of the moderator in the control cavities and increase the size of the vapor bubbles in the control cavities. This can cause the moderator liquid to be displaced from the bottom of the cavities, reducing the measured density of the moderator and increasing the average speed of the neutrons diffusing from the moderator into the fuel and thereby decreasing the fission rate.
[00158] In at least some exemplary embodiments of the revealed nuclear reactor system, because the vapor bubble in the control cavities can be much less dense than the moderator liquid in the control cavities and the vapor bubble can vary in size from Substantially non-existent for almost the size of the entire control cavity, the system can allow the average density of the moderator in the core to vary from the complete density of the moderator liquid to less than 15% of the complete density. This can allow control of the reactor under varying fuel reactivity conditions ranging from enriched fuel without xenon load to moderately used fuel with an equilibrium xenon load for fuel with a high exhaust and high load resulting from absorber fission by-products. neutron. This can be achieved substantially without loss of neutrons to control absorbers and provides substantially maximum production of new fissile fuel and a substantially maximum fuel conversion ratio at all points in the fuel life cycle.
[00159] The revealed nuclear reactor system can be used in any application with the use of a generated nuclear power. For example, the revealed nuclear reactor system can be used in any application with the use of steam (H2O) generated by the use of the power of a nuclear reaction. The operation described below can generally apply to an operation of all revealed modalities of the nuclear reactor system 5. Additionally, as described below, some subsystems of the revealed nuclear reactor system can be used in additional applications other than the generated nuclear power.
[00160] Referring to Figure 3, a nuclear reactor system operation 5 can be initiated when fuel is supplied in the fuel assembly 125, 125 ', 125a, or 125b that has fuel tubes 135, 135', 135a and / or 135b. When reactor 15 is started with fresh fuel in tubes 135, 135 ', 135a and / or 135b, the level of the moderator in the control cavity matrix 130, 130', 130a and / or 135b can stabilize at the equilibrium level based on in the reactor design and fuel reactivity included in fuel tubes 135, 135 ', 135a and / or 135b. Over an initial period (for example, a few days), the levels of xenon 135 and samarium-149 neutron absorber rise to equilibrium levels and the moderator's cooling rate can be kept substantially constant by a refrigerant subsystem operation reactor 25 (the general operation of the reactor refrigerant subsystem will be described in more detail below). While the reactor refrigerant subsystem 25 is operated to provide a constant rate of cooling of the moderator in the control cavity matrix 130, 130 ', 130a and / or 130b, the level of xenon and samarium in the fuel will rise and the reactivity of the reactor 15 will slowly drop below one, causing the reaction rate to decrease and the energy deposited in the moderator to decrease so that some of the moderator vapor condenses. Therefore, more moderator is extracted into control cavities 140, 140 ', 140a and / or 140b, which raise the level of the moderator and the average moderator density. This will decrease the number of neutrons that undergo resonance capture and thereby compensate for the neutrons that are absorbed by the gradually increasing amounts of xenon and neutron-absorbing samarium in reactor fuel 15. Therefore, using control cavity matrix 130 as a For example, the size of liquid zones 190 and 275 in the control cavity matrix 130 can be increased and the size of gas zones 185 and 280 in the control cavity matrix 130 can be decreased. A similar effect occurs in the other revealed modalities.
[00161] If reactor 15 has a conversion ratio greater than one, or is primarily supplied with U235 and U238, during steady state operation there is a period of time during which the fuel reactivity can increase because more fissile fuel is created than used or because Pu239 is being created from U238 as U235 is burned (because Pu239 is more reactive than U235). If this occurs, the fission rate will rise while the cooling remains constant, more neutrons will deposit energy in the moderator, the evaporation rate in the control cavities 140, 140 ', 140a and / or 140b will be higher than the condensation rate and moderator liquid will be displaced from control wells 140, 140 ', 140a and / or 140b by excess moderator steam. This causes less moderation than neutrons and an increase in the number of neutrons absorbed in the fertile U238 (or Th232), decreasing the number of thermal neutrons available to cause fission and reducing the reaction rate to the rate at which as much energy as possible is deposited in control cavities 140, 140 ', 140a and / or 140b as it is removed by reactor refrigerant subsystem 25. The level of the moderator liquid will gradually decrease as long as fuel reactivity continues to rise (for example, over a period that can last from days to years). During that period, the fissile content of the fuel may increase and may continue to increase for the next period of time (discussed below).
[00162] Over the next period of time (for example, the next months or years), as the fissile content of the fuel is reduced by exhaustion and the level of neutron-absorbing fission by-products rises, the negative feedback mechanism of control cavities 140, 140 ', 140a and / or 140b can operate to cause the moderator level in the control cavity matrix 130, 130', 130a and / or 130b to rise very slowly to compensate for the reactivity of the fuel being diminished by exhaustion. Eventually, the moderator level will rise to the top of the control cavity matrix 130, 130 ', 130a and / or 130b and reactor 15 will become subcritical and will stop producing power. Therefore, using the control cavity matrix 130 as an example, there will be no substantially gaseous zones 185 and 280 in the control cavity matrix 130 at this time. A similar effect occurs in the other revealed modalities. When reactor 15 stops, the xenon 135 that has been produced so far by reactor 15 continues to drop, so that in a relatively short period of time (for example, a day or two), enough xenon 135 will decrease so that reactor 15 can be restarted again. When reactor 15 is restarted, reactor 15 can be run until the xenon concentration 135 rises again in a relatively short period of time (for example, a few days). Because the equilibrium concentration of xenon 135 changes proportionally to the power level, the operation of the reactor 15 can continue for relatively longer durations as the power level of the reactor 15 is reduced.
[00163] After the initialization procedure described above, the reactor 15 can be maintained in a steady state operation. In steady state operation, energy is produced by fission of fuel atoms in fuel tubes 135, 135 ', 135a and / or 135b. Most of that energy is deposited on fuel rods arranged in fuel tubes 135, 135 ', 135a and / or 135b as heat, which is extracted from fuel rods in fuel tubes 135, 135', 135a and / or 135b by a flow of reactor refrigerant through the fuel pipes 135, 135 ', 135a and / or 135b that is provided by an operation of the reactor refrigerant subsystem 25 and pump subsystem 30. Before proceeding with the description of the steady state of reactor 15 and reactor core 100, the operation of reactor refrigerant subsystem 25 and pump subsystem 30 will be described.
[00164] Referring to Figures 2, 3 and 13, the transfer subsystem 305 of the reactor refrigerant subsystem 25 transfers reactor refrigerant between the heat exchanger 20 and the reactor core 100, 100 ', 100a, or 100b . The cooling pump 390 of the pump subsystem 30 can pressurize a flow of reactor refrigerant in the cold reactor refrigerant passage 320 of the transfer subsystem 305 to transfer the cold reactor refrigerant from the heat exchanger 20 to reactor 15. The refrigerant of cold reactor flowing in passage 320 can thereby flow through the openings of the containment structure 85 and into the reflective zone 95.
[00165] The cold reactor refrigerant flowing in the cold reactor refrigerant passage 320 may flow into the passages 330 of the fuel refrigerant subsystem 310. The cold reactor refrigerant flowing in the passages 330 passes through the fuel pipes 135, 135 ', 135a and / or 135b to facilitate heat exchange with fuel tubes 135, 135', 135a and / or 135b. The fuel pipes 135, 135 ', 135a and / or 135b provide heat by transferring heat to the cold reactor refrigerant flowing through passages 330, thereby pouring the cold reactor refrigerant into the hot reactor refrigerant. Therefore, the reactor refrigerant leaves the fuel pipes 135, 135 ', 135a and / or 135b with more energy per pound than the reactor refrigerant had when entering the fuel pipes 135, 135', 135a and / or 135b, either by increasing the temperature of the reactor refrigerant or by changing the reactor refrigerant from a liquid to a gaseous state, or both. The passages 330 can then transfer the hot reactor refrigerant to the hot reactor refrigerant passage 325 of the transfer subsystem 305.
[00166] In the first embodiment described, a portion of the cold reactor refrigerant flowing in cold reactor refrigerant passages 330 also flows in passages 335 of the moderator refrigerant subsystem 315. The cold reactor refrigerant flowing in passages 335 passes through control cavities 140 to facilitate heat exchange with control cavities 140. The cold reactor refrigerant flowing in passage 335 is heated, in a way, through heat exchange by the moderator confined within control cavities 140, and it is transmitted out of control cavities 140 through passages 335 and back to passages 330. The cold reactor refrigerant flowing through passages 330 passes through the water mirror 105. The cold reactor refrigerant flowing through passages passages 330 is heated, in a way, through heat exchange by the water mirror moderator 105. The reactor refrigerant flowing in passages 330 can then pass through of the fuel pipes 135 and thus be heated from cold reactor refrigerant to hot reactor refrigerant. The passages 330 can then transfer the hot reactor refrigerant to the hot reactor refrigerant passage 325 of the transfer subsystem 305.
[00167] The reactor refrigerant flowing through the passage 335 of the moderator refrigerant subsystem 315 can flow, for example, in the arrangement depicted in Figure 14. The reactor refrigerant from the cold reactor refrigerant passage 320 of the transfer subsystem 305 can flow in passage 335 through an intermediate passage 330 and an inlet member 350. The reactor refrigerant then flows through channel 380 of inner member 355. Some of the reactor refrigerants can flow over an entire length of a channel 380 until they reach end portion 370. However, some of the reactor refrigerants can also flow directly from channel 380 to channel 385, through openings 375, before reaching end portion 370. Since the relatively cold reactor refrigerant passes directly in channel 385 through openings 375 and mixes with the relatively hot reactor refrigerant in channel 385, one has The temperature of the reactor refrigerant in channel 385 can remain relatively constant along the length of passage 335. The sizes and / or spacing of openings 375 can be designed to maximize the maintenance of a generally constant temperature in channel 385. For example, the quantity of reactor refrigerant mixing between channels 380 and 385 can increase in a direction that moves to end portion 370. The reactor refrigerant then flows through channel 385 and back to the reactor refrigerant passage 330 of the transfer subsystem 305, through an outgoing member 365.
[00168] The cooling pump 390 of the pump subsystem 30 can pressurize a cold reactor refrigerant flow in the cold reactor refrigerant passage 320 of the transfer subsystem 305 through the fuel tubes 135 and a hot reactor refrigerant flow from the reactor 15 back to heat exchanger 20 through the passage of hot reactor refrigerant 325.
[00169] The fission of fuel in fuel tubes 135, 135 ', 135a and / or 135b produces energetic neutrons with a higher speed (for example, neutrons that move at a relatively intermediate or high speed). These higher speed energetic neutrons deposit energy in the control cavity matrix moderator 130, 130 ', 130a and / or 130b through collision with moderator atoms. Higher speed energy neutrons are decelerated to a low energy state ("slow neutrons") through these collisions with the moderator atoms, and with some slow neutron collisions, the fission of the fuel atoms is then caused. The reactor can be considered stable (for example, at constant power output) when, for each fission of a fuel atom, one of the produced neutrons causes a fission. Therefore, the reactor can be considered stable when, on average, exactly one of the neutrons produced through the fission of a fuel atom causes a new fission.
[00170] As the moderator in the control cavity matrix 130, 130 ', 130a and / or 130b is heated by energetic neutrons, some of the moderators may evaporate in a steam moderator (for example, boiling in a gaseous state). Steam moderator in the gaseous state is less dense than the liquid moderator (for example, in a liquid state) and ascends to the upper portion of the control cavities 140, 140 ', 140a and / or 140b in which it will be confined by the fact that that control cavities 140, 140 ', 140a and / or 140b are closed in an upper portion and can therefore confine the moderator in an upper portion. Since the volumes of control cavities 140, 140 ', 140a and / or 140b can be constant, the low density gas vapor moderator that is confined and accumulates in the upper portions of control cavities 140, 140', 140a and / or 140b will dislodge the higher density liquid moderator out of the lower portions of control cavities 140, 140 ', 140a and / or 140b. Therefore, the overall average density of the moderator in the control cavities 140, 140 ', 140a and / or 140b is reduced. To substantially prevent any moderator in control cavities 140, 140 'and 140a from becoming a steam moderator, control cavities 140, 140', 140a and / or 140b are cooled by the reactor refrigerant subsystem 25. The reactor refrigerant subsystem 25 can cause some of the gas vapor moderators to condense into the denser liquid moderator. Less steam moderator will therefore be confined to the upper portions of control cavities 140, 140 ', 140a and / or 140b, so that the relatively smaller high density liquid moderator will be dislodged out of control cavities 140, 140 ', 140a and / or 140b. Consequently, the liquid moderator will flow back into control wells 140, 140 ', 140a and / or 140b through the open lower portions and / or side portions of control wells 140, 140', 140a and / or 140b.
[00171] Referring to Figures 7 and 8 and using control cavity matrix 130 as an example, the reactor refrigerant subsystem 25 can remove less energy by transferring heat from the confined moderator in the cavity matrix to control 130. Consequently, a moderator increase amount will be heated by energetic neutrons in the steam moderator. Therefore, as an amount of steam moderator increase is confined and accumulates in the upper portions of control cavities 140, boundary 195 will fall as an amount of liquid moderator increase is dislodged out of the control cavities. 140 (for example, evicted under intermediate member 170 and end member 165). Therefore, gas zone 185 will increase in size and liquid zones 190 will decrease in size. Similarly in cone assembly 150, as a reactor refrigerant subsystem 25 removes less energy through heat transfer, an increased amount of vapor moderator is confined and accumulates in the upper portions of inner cone assemblies 200 and outer cone sets 205. Therefore, limit 290 will fall as an increasing amount of the liquid moderator is dislodged out of inner cone sets 200 and outer cone sets 205 (for example, dislodged under the inner cone 235 and under the outer cone 240). Therefore, gas zone 280 will increase in size and liquid zones 190 and 275 will decrease in size. A similar effect occurs in the order revealed in the reactor modalities 15.
[00172] The reverse effect also occurs. Again with the use of control cavity matrix 130 as an example, the reactor refrigerant subsystem 25 can remove more energy by transferring heat from the moderator confined in the control cavity matrix 130. Consequently, a decreased amount of moderator will be heated by the energetic neutrons in the steam moderator. Therefore, as a decreasing amount of the vapor moderator is confined and accumulates in the upper portions of the control cavities 140, the limit 195 will rise as the liquid moderator re-enters the control cavities 140 (for example , re-enters intermediate member 170 and end member 165). Therefore, gas zone 185 will decrease in size and liquid zone 190 will increase in size. Similarly in the cone assembly 150, as the reactor refrigerant subsystem 25 removes more energy through heat transfer, a decreased amount of the vapor moderator is confined and accumulates in the upper portions of the inner cone assemblies 200 and in the outer cone sets 205. Therefore, the limit 290 will rise as an increase amount of the liquid moderator re-enters the inner cone sets 200 and outer cone sets 205 (for example, enters again under the inner cone 235 and under outer cone 240). Then, gas zone 280 will decrease in size and liquid zones 190 and 275 will increase in size. The steam moderator can also condense along the sides of the control cavities 140 and drip into liquid zones 190 and 275. A similar effect occurs in other revealed modes of the reactor 15.
[00173] When the reactor refrigerant subsystem 25 operates to extract, substantially, all energy from the control cavity matrices 130, 130 ', 130a and / or 130b as it is deposited from the fuel in fuel pipes 135, 135 ', 135a and / or 135b, the evaporation rate and the condensation rate in the control cavities 140, 140', 140a and / or 140b will be substantially the same and the size of the gas zones 185, 185 ', 185a, 280 and / or 185b will remain substantially constant. Therefore, there will be substantially no movement of the moderator inside or outside control cavities 140, 140 ', 140a and / or 140b.
[00174] Neutrons with higher speed can be decelerated through collisions with the moderator atoms when the moderator atoms are either in a liquid state (liquid moderator) or in a gaseous state (vapor moderator). When the average density of the moderator is decreased (for example, by increasing the size of the gas zones 185, 185 ', 185a, 280 and / or 185b), an average distance between the moderator atoms is increased and an average distance in the which neutrons need to take off between collisions is increased. When the neutrons with the highest speed move further between each other, they spend more time at the higher speeds and so the average number of neutrons that move is relatively high and the intermediate speed is higher. Although slow neutrons may have a relatively high probability of causing fission when they collide with fuel atoms arranged in fuel tubes 135, 135 ', 135a and / or 135b, higher speed neutrons may have a relatively high probability being absorbed into reactor 15 without causing fission. Consequently, the number of slow neutrons available to cause fission will decrease.
[00175] When the reactor 15 operates at a steady state operating level, the reactor refrigerant subsystem 25 can operate to maintain the gas zones 185, 185 ', 185a, 280 and / or 185b at a desired substantially constant size. This desired size of the gas zones 185, 185 ', 185a, 280 and / or 185b can provide a desired density of the moderator within the control cavity matrix 130, 130', 130a and / or 130b so that only neutrons with more speed high enough will be absorbed at intermediate and high speeds so that there is a desired amount of remaining slow neutrons moving at relatively low speeds to cause a new fission for each old fission in the 125, 125 ', 125a and 125b fuel assemblies.
[00176] The gas zones 185, 185 ', 185a, 280 and / or 185b can be maintained at a substantially desired constant size through the use of negative feedback. As described above, reactor refrigerant subsystem 25 can be controlled to be substantially compatible with the reactor core cooling rate 100, 100 ', 100a and 100b (for example, by controlling refrigerant flow through the control cavity 130, 130 ', 130a and / or 130b) with the fission rate (and thus the heating rate transmitted to the moderator in the control cavity matrices 130, 130', 130a and / or 130b through the fission in fuel assemblies 125, 125 ', 125a and 125b) of reactor core 100, 100', 100a and 100b. If the rate of heat heating transmitted to the control cavity matrices 130, 130 ', 130a and 130b through the fission in the fuel assembly 125, 125', 125a and 125b is greater than the cooling rate provided through the heating subsystem reactor refrigerant 25, the gas zones 185, 185 ', 185a, 280 and / or 185b will expand. The expansion of gas zones 185, 185 ', 185a, 280 and / or 185b decreases the average density of the moderator in the control cavity matrices 130, 130', 130a and / or 130b, which increases the percentage of neutrons lost by absorption at intermediate and high speeds (resonance capture), therefore, the percentage of slow neutrons available to cause fission decreases, which decreases the heating rate of the reactor 15. If the heating rate is lower than the cooling rate, the zones gaseous 185 185 ', 185a, 280 and / or 185b will compress, increasing the average density of the moderator in the control cavity matrices 130, 130', 130a and / or 130b, decreasing the percentage of neutrons lost by resonance capture, therefore, increasing the percentage of slow neutrons available to cause fission, which increases the rate of heating. Therefore, reactor 15 is controlled to make the reaction rate follow the cooling rate of the control cavity matrix 130, 130 ', 130a and / or 130b through the reactor refrigerant subsystem 25. Consequently, the increase or decreasing the cooling rate of the control cavity matrix 130, 130 ', 130a and / or 130b will cause will cause a corresponding increase or decrease in the total power output of the reactor 15. Because the amount of energy from the reactor deposited in the moderator is only a small amount (for example, approximately between 1% and 5%, such as, for example, approximately 3%) of the total energy produced by the reactor 15, only a relatively small amount of energy (and corresponding heat) of the total energy produced by the reactor 15 is adjusted by a relatively small cooling rate (in relation to the total energy produced by the reactor 15) to maintain control of the reactor 15. So, control a relative cooling rate The small size allows simple and stable control of the total power output of the reactor 15, which is, for example, approximately 30 times greater than the amount of heat and energy that is transmitted to the moderator (and which is controlled by adjusting the cooling).
[00177] Just to illustrate a comparison between the total power output of the relatively wide reactor 15 and the relatively small amount of energy transmitted to a moderator, an example of a reactor to supply power to a 1,000 Megawatt electrical power generator can be considered. A total energy produced through the exemplary power generator can be approximately 10,000,000,000 BTU / hour when the generator runs at full power. If the moderator is heavy water (D2O) at a temperature around 282 ° C (540 degrees Fahrenheit), the reactor core can contain, for example, around 100 tons of moderator. Assuming that 3% of the total energy produced by the reactor is deposited in the moderator's core, then the amount of energy transmitted to the moderator can be around 300,000,000 BTU / hour or 1,500 BTU / hour per pound of the moderator. At this rate, even if no cooling has been provided, it can take approximately 25 minutes to evaporate each pound of moderator. Since the gaseous steam moderator can be approximately 20 times less dense than the liquid moderator at that exemplary temperature, it can take approximately one minute to boil the moderator enough to dislodge the liquid moderator's pound residue from the cavities control 140, 140 ', 140a and / or 140b in this example. This example is provided purely to show the relative amount of energy transmitted to the moderator. The method and apparatus disclosed can be used in any type or size of nuclear reactor system.
[00178] Reactor 15 can supply energy from a nuclear reaction to supply power to a generation 10 subsystem at any suitable time during its operation. An example of how the reactor 15 supplies power to the power generation subsystem 10 will now be provided, using steady-state operation as an illustrative example. The reactor 15 can also supply power to the generation 10 subsystem during other phases and operating states of the nuclear reactor system 5.
[00179] Referring to Figures 1 and 13, the cooling pump 390 pressurizes a reactor refrigerant flow through the cold reagent cooler passage 320 and the hot reactor refrigerant passage 325 of the reactor refrigerant subsystem 25. With this, the reactor refrigerant subsystem 25 transports the hot reactor refrigerant to the steam generators arranged in the heat exchanger 20 via the hot reactor refrigerant passage 325. The hot reactor refrigerant flowing through the steam generator tubes boils water (H2O), which was delivered to the heat exchanger 20 through the turbine steam subsystem 65 (as further explained below), through heat transfer. While passing through the heat exchanger 20, the reactor refrigerant flowing through the hot reactor refrigerant passage 325 is cooled by transferring heat between the reactor refrigerant and water (H2O) in the heat exchanger 20. The reactor refrigerant The cooled coolant is then returned to the reactor 15 subsequently through the passage of cold reagent refrigerant 320 from the reactor refrigerant subsystem 25. The reactor refrigerant subsystem 25 repeats this cycle, continuously, transferring a desired amount of refrigerant from hot reactor, which was heated by reactor 15, to heat exchanger 20 and then subsequently returning the cooled reactor refrigerant to reactor 15. The high pressure (H2O) steam generated through the heat exchanger 20 steam generators is then transferred to a turbine 45 via a passage 70 of turbine steam subsystem 65 (from power generation subsystem 10) based on a flow of steam (H2O) and water (H2O) produced by an H2O 395 pump. The H2O 395 pump pressurizes a flow of steam (H2O) and water (H2O) in the heat exchanger 20, in passage 70, in the turbine passages 45, in passage 75, in the turbine cooling subsystem 60 and in passage 80.
[00180] The turbine 45 converts the high pressure steam (H2O) that is delivered through the passage 70 of the turbine steam subsystem 65 into mechanical energy. For example, steam (H2O) stimulates the plurality of elements in the exemplary rotating rod of turbine 45 described above and expands from the series of exemplary cylinders described above to drive turbine rod 45. This turbine operation 45 simply illustrates a among any suitable methods to produce mechanical energy from steam (H2O). The mechanical energy of the exemplary turbine rod 45 is then mechanically transferred to drive the assembly 50 of the power generation subsystem 10.
[00181] The drive set 50 then mechanically transfers the mechanical energy transmitted to generator 55 of the power generation subsystem 10 via the exemplary drive rod set described above or through any other suitable mechanical connection. Thus, the drive assembly 50 can drive generator 55 to produce electricity. As an example, generator 55 generates AC electricity at any suitable frequency such as, for example, a power of 50 Hz (cycle 50) or 60 Hz (cycle 60). Electricity from generator 55 is then supplied using conventional transfer techniques to a power grid or any other location or activity that uses electricity.
[00182] Passage 75 of turbine steam subsystem 65 transfers dead or superfluous steam (H2O) from turbine 45 to turbine cooling subsystem 60 of power generation subsystem 10. Turbine cooling subsystem 60 uses any suitable technique such as, for example, using condensers, cooling towers, forced air flow and / or cooling by a single passage to condense steam (H2O) into water (H2O). The relatively cold water (H2O) is then transferred from the turbine cooling subsystem 60 to the heat exchanger 20 via a passage 80.
[00183] The relatively cold water (H2O) delivered to the heat exchanger 20 through a passage 80 of the turbine steam subsystem 65 enters the heat exchanger 20. Some of the relatively cold water (H2O) enters the lower inner portion of the heat exchanger 20 and some of the relatively cold water (H2O) enters the heat exchanger 20 in the upper and / or upper portion of the heat exchanger 20. The relatively cold water (H2O) that enters the lower inner portion is heated and boiled through the heat transfer with the hot reactor refrigerant transferred in the heat exchanger 20 through the hot reactor refrigerant passage 325 of the reactor refrigerant subsystem 25. The relatively cold water (H2O) that enters the upper portion is injected in the lower inner portion of the heat exchanger 20 by means of the plurality of nozzles 83 arranged in the upper and / or central portion of the heat exchanger 20, in the inner walls of the heat exchanger 20. The plurality of nozzles 8 3 injects the water (H2O) into the boiling water (H2O) contained within the inner portion of the heat exchanger 20. The relatively cold water (H2O) mixes with the boiling water (H2O) to help reduce the magnitude of the gradient H2O temperature contained within the heat exchanger 20. The exemplary illustration above of the water transfer (H2O) to the heat exchanger 20 is provided purely as an example and any known technique suitable for heat exchange can be used in the heat exchanger 20 .
[00184] The process described above using energy from a nuclear reaction in reactor 15 to produce steam (H2O) in heat exchanger 20 that uses steam (H2O) to drive turbine 45 and which drives generator 55 through the turbine 45 is repeated, continuously, to produce a desired amount of electricity. Similarly, the process of condensing steam (H2O) into water (H2O) and returning water (H2O) to the heat exchanger 20 is repeated, continuously, as desired. Therefore, this process is repeated, continuously, as desired as the reactor 15 supplies power to the power generation subsystem 10 to produce energy such as, for example, electricity.
[00185] As the nuclear reactor system is in a steady state operation, power demands may vary. Power demands can vary on a day-to-day basis. Depending on the time of day, or during the night, the average power demands may change (for example, the power demands may be lower in the middle of the night on a weeknight, as compared to during the morning of the week or on a night over the weekend). Reactor control subsystem controller 540 can be operated to vary a power output from nuclear reactor system 5. Controller 540 can be operated to control a reactor control subsystem 40 and a pump subsystem 30 to vary a cooling rate of reactor refrigerant and / or moderator refrigerant in reactor 15, thus a power output of nuclear reactor system 5 is varied through the use of negative feedback.
[00186] When controller 540 is desired for a nuclear reactor system 5 to generate a greater amount of power, it is controlled to operate reactor control subsystem 40 and pump subsystem 30 to increase a moderator cooling rate in reactor 15 so that the moderator's cooling rate is greater than the moderator's heating rate through the fuel pipes 135, 135 ', 135a and / or 135b. Controller 540 controls cooling pump 390 to cause a relatively larger amount of reactor refrigerant to flow through reactor 15. If the cooling rate delivered through a reactor refrigerant subsystem 25 to the moderator in the control cavity arrays 130, 130 ', 130a and / or 130b is greater than the heating rate of the heat transmitted to the moderator in the control cavity matrix 130, 130', 130a and / or 130b through the fission in the fuel assembly 125, 125 'and 125a, gas zones 185, 185 ', 185a, 280 and / or 185b will retract. The retraction of gas zones 185, 185 ', 185a, 280 and / or 185b increases the average density of the moderator in the control cavity matrices 130, 130', 130a and / or 130b, which decreases the percentage of neutrons lost by capture by resonance, therefore, the percentage of slow neutrons available to cause fission and the reactor heating rate 15 are increased. By increasing the heating rate of the reactor 15, a greater amount of heat will be transmitted to the reactor refrigerant flowing in the hot reactor refrigerant passage 325, and therefore a greater amount of heat will be transferred through the reactor refrigerant subsystem. 25 to the heat exchanger 20. Thus, heat exchanger 20 will produce a greater amount of steam (H2O) and a greater amount of steam (H2O) will be transferred from heat exchanger 20 to turbine 45 via passage 70. O controller 540 is also operated to cause the H2O pump 395 to cause a greater flow of steam (H2O) to be transferred to turbine 45. The greater amount of steam (H2O) will cause turbine 45 to produce a greater amount of energy mechanics which, when transferred from turbine 45 to generator 55 via drive assembly 50, will cause generator 55 to produce a relatively greater amount of power (e.g., electricity).
[00187] When it is desired that the nuclear reactor system 5 generates a smaller amount of power, the controller 540 is operated to control the reactor control subsystem 40 and the pump subsystem 30 to decrease a moderator cooling rate in the reactor 15 so that the moderator cooling rate is less than the moderator heating rate through the fuel pipes 135, 135 ', 135a and / or 135b. Controller 540 controls cooling pump 390 to cause a relatively smaller amount of reactor refrigerant to flow through reactor 15. If the cooling rate delivered through reactor refrigerant subsystem 25 to the moderator in control cavity arrays 130 , 130 ', 130a and / or 130b is less than the heat rate of heat transmitted to the moderator in the control cavity matrix 130, 130', 130a and / or 130b through the fission in the fuel assembly 125, 125 'and 125a , the gas zones 185, 185 ', 185a, 280 and / or 185b will expand. The expansion of gaseous zones 185, 185 ', 185a, 280 and / or 185b decreases the average density of the moderator in the control cavity matrices 130, 130', 130a and / or 130b, which increases a percentage of neutrons lost through the capture by resonance, therefore, decreasing the percentage of slow neutrons available to cause fission and decreasing the heating rate of reactor 15. By decreasing the heating rate of reactor 15, a smaller amount of heat will be transmitted to the reactor refrigerant that flows through the hot reactor refrigerant passage 325 and less heat will therefore be transferred through reactor refrigerant subsystem 25 to heat exchanger 20. Thus, heat exchanger 20 will produce a smaller amount of steam (H2O ) and a smaller amount of steam (H2O) will be transferred to heat exchanger 20 to turbine 45 via passage 70. Controller 540 is also operated to make the H2O pump 395 cause less fl flow of steam (H2O) is transferred to turbine 45. The smaller amount of steam (H2O) will cause turbine 45 to produce a smaller amount of mechanical energy which, when transferred from turbine 45 to generator 55 via drive assembly 50 , will cause generator 55 to produce a relatively smaller amount of power (for example, electricity).
[00188] The retraction and / or expansion of gas zones 185, 185 ', 185a, 280 and / or 185b can be very gradual and / or light and still provide sufficient control of the nuclear reactor system 5. So even a small change in the volume of gas zones 185, 185 ', 185a, 280 and / or 185b can provide a difference large enough to affect resonance capture and to control reactor 15 sufficiently through negative feedback.
[00189] The operation of the reactor core 100b can generally follow the operation of the reactor cores 100, 100 'and 100a described above. As depicted in Figures 121, 12J and 12K, reactor 100b provides additional features to confine the moderator to the control cavity matrix 130b that can be used, for example, with a higher percentage of fast fission.
[00190] As shown in Figures 121, 12J and 12K, the relatively cold moderator is free to move from the water mirror 105 and to the moderator coolant inflow tube 335b. The moderator disposed in the moderator coolant inflow tube 335b is then free to move in the control wells 140b through holes 336b, so the moderator in the control wells 140b is cooled. A substantially equal volume of a warmer moderator moves out of the control cavity 140b and in the moderator flow tube 337b through holes 338b. The moderator in moderator flow tube 337b is free to move from moderator flow tube 337b to reflective zone 95. Since control cavities 140b have closed upper portions, the moderator may not be free to move between the upper portions of control cavities 140b and reflective zone 95.
[00191] With reference to Figure 12N, the revealed modality can operate when, for example, the moderator is cooled by the circulation of the relatively cooled moderator through and in the water mirror 105 and / or control cavity 140b (and / or 140 'and / or 140a). The embodiment of Figure 12N can operate based on the stability of the vapor moderator pressure at substantially all points in the system and the stability of the height of limit 115 disposed on top of the water mirror 105 above fuel rods 127b (e / or similar fuel rods arranged in the reactor core 100 'and 100a). The moderator cooling tube 327b (and / or similar moderator cooling tubes arranged in the reactor core 100 'and 100a) allows the moderator flow from the reflecting zone 95 and control cavities 140b (and / or control cavities 140' and / or 140a) in moderator heat exchange tubes 390b that pass through tank 377b to passage 355b and moderator cooling pump 350b. The moderator cooling rate can be, for example, the pump flow rate multiplied by the difference in temperature between water temperature (H2O), temperature in tank 377b and moderator temperature in water mirror 105. Due to the temperature difference can be kept at a constant level, the moderator control cavity cooling rate and, therefore, the total power output of the reactor is proportional to the pump flow rate. Therefore, improper operation of the moderator cooling pump 350b and / or an interruption of the pump power will shut down the reaction in reactor 15. The refrigerated moderator flows from the moderator cooling pump 350b via passage 322b (and / or similar passage arranged in reactor cores 100 'and / or 100a) for moderator coolant inflow tubes 335b (and / or similar tubes arranged in reactor cores 100' and / or 100a). A capacitor and differential flow portion similar in shape and function to capacitor 570 and differential flow portion 675 of load tracking subsystem 515 can be inserted into passage 322b adjacent to pump 350b.
[00192] The reactor control subsystem operation 40 will now be described, starting with a description of an exemplary 515 load tracking subsystem operation. The reactor control subsystem operation is controlled via a 540 controller of the control subsystem. control 510.
[00193] As shown in Figure 20, port 545 of load monitoring subsystem 515 selectively reduces a flow of steam (H2O) from heat exchanger 20 to turbine 45 through passage 70 through the diversion of steam (H2O) from the passage 70 in passage 555. To divert steam (H2O) in passage 555, door 545 is moved from the closed position to the partially open position or the fully open position. When port 545 is in the closed position, substantially all of the steam flow (H2O) flows from passage 70 to turbine 45. When port 545 is moved to the partially open position (for example, when the desired steam flow to turbine 45 must decrease to suit a lower electric energy demand), the excess steam (H2O), which is proportional to the amount by which port 545 is opened, flows from passage 70 to passage 555. Therefore, the operation from port 545 controls the amount of steam (H2O) that is diverted from passage 70 at passage 555. An operation of port 550, which is similar to the operation of port 545, controls an amount of steam (H2O) that is diverted from the passage 555 in passage 560. The steam (H2O) that flows in passage 560 is transferred directly to the turbine cooling subsystem 60 through passage 560. Therefore, a port 550 operation controls the amount of steam flow (H2O) that bypasses turbine 45 and is transferred directly for the turbine cooling subsystem 60. Depending on its position and operating similarly to port 545, port 550 can divert substantially all of the flow, substantially no flow or part of the vapor flow (H2O) from passage 555 to the turbine cooling subsystem 60 through passageway 560. When a rapid shutdown of turbine 45 is desired, port 545 is moved to the open position to transfer substantially the entire flow of steam (H2O) from passageway 70 to passageway 555 and the port 550 is moved to the open position to transfer substantially all of the vapor flow (H2O) from passage 555 to passage 560. Therefore, substantially all of the vapor flow (H2O) from heat exchanger 20 is diverted to the air-cooling subsystem turbine 60, which facilitates quick shutdown of turbine 45.
[00194] Steam (H2O) that flows through passage 555 that is not diverted to turbine cooling subsystem 60 through passage 560, flows to condenser 570 through passage 565 or may flow to a similar condenser (not shown ) at passage 322b, as shown in Figure 12N. Due to the heat exchange between the steam (H2O) disposed in condenser 570 and cold reactor refrigerant flowing through the passage of cold reactor refrigerant 320, part or substantially all the steam (H2O) disposed in condenser 570 condenses in water (H2O ). Valve 575 operates to allow water (H2O) to flow out of condenser 570 while substantially blocking a flow of steam (H2O) out of condenser 570. Water (H2O) then flows from condenser 570 to heat exchanger 585 through passage 580. The heat exchanger 585 cools a water temperature (H2O) to a desired temperature (e.g., a temperature substantially equal to that of water (H2O) being transferred through passage 80 of the turbine steam subsystem 65). Passage 590 then transfers water (H-O) from heat exchanger 585 to passage 80 through junction 595. Passage 80 then transfers water (H2O) to an inlet of pump 395 of pump subsystem 30.
[00195] Thus, the load monitoring subsystem 515 allows control of turbine 45 by adjusting port 545 to direct more or less steam (H2O) from heat exchanger 20 to pass through turbine 45 as the energy demand fluctuates. In some cases of normal operation, excess steam (H2O) is used to preheat the input raw material from the turbine cooling subsystem 60 to the heat exchanger 20. In addition, part of the excess steam (H2O ) can be used to heat the primary moderator control cavity refrigerant through a heat exchanger (for example, a small heat exchanger) arranged in passage 322b or passage 320, which therefore reduces the cooling of the cavities of control 140, 140 ', 140a and / or 140b and the energy output of the reactor when an amount of excess steam (H2O) increases (or increases the energy output when an amount of excess steam (H2O) decreases).
[00196] An exemplary 520 bypass subsystem operation will now be described. The pump 600 is controlled by controller 540 to selectively pressurize the reactor refrigerant in passage 605 to the reactor refrigerant pump in the hot reactor refrigerant passage 325 in the cold reactor refrigerant passage 320, thus bypassing the heat exchanger 20 and pump 390. Therefore, pump 600 and passage 605 allow the relatively hot reactor refrigerant flowing through the hot reactor refrigerant passage 325 bypass the heat exchanger 20 and flow directly into the cold reactor refrigerant passage 320 , which allows the hot refrigerant to mix with the relatively cold refrigerant and raise the temperature of the refrigerant flowing in the cold reactor refrigerant passage 320 at the desired times during operation of the reactor 15 (for example, during shutdown, operation low energy and / or initial reactor refrigerant charging).
[00197] Therefore, the bypass subsystem 520 allows a relatively small amount of primary refrigerant to be forced from the normal refrigerant path, bypassing the heat exchanger 20 and / or the reactor core 100, 100 ', 100a, and / or 100b. The bypass subsystem 520 can operate when the cooling pump 390 and / or H2O pump 395 are driven by a single motor and proportional amounts of fluid are pumped through the transfer subsystem 305 to balance an amount of heat entering the heat exchanger heat 20 through the passage of hot reactor refrigerant 325 and an amount of heat leaving the heat exchanger 20 through the flow of steam (H2O) through passage 70 to turbine 45 during normal operation. At low energy, significant temperature deviations can occur (for example, greater temperature deviations than at full power) and these temperature deviations can change the flow rate between a primary refrigerant flow rate through the passage of hot reactor refrigerant 325 and a flow rate of the turbine raw material through the passage 70 outside a desired flow rate. The operation of the diversion subsystem 520 compensates for these temperature deviations and maintains the flow ratio between a primary refrigerant flow rate through the hot reactor refrigerant passage 325 and a turbine raw material flow rate through passage 70 at a desired flow rate. In response to these temperature deviations, the pump 600 can operate at a relatively low capacity. For example, the capacity of pump 600 can be 3% of the capacity of pump 390 at full power, which can correspond to 30% of pump capacity 390 to 10% energy, which can be sufficient capacity for the pump 600 compensate for a significant imbalance in the desired flow rate. Pump 600 can also operate in situations when it is not desirable to pass any turbine feedstock through passage 70 to turbine 45, but it is desirable to maintain a small flow of primary reactor refrigerant through the reactor core 100, 100 ', 100a and / or 100b (for example, in the initialization of the reactor to bring the reactor core 100, 100 ', 100a and / or 100b evenly up to the operating temperature).
[00198] An exemplary operation of the moderator stabilization subsystem 525 will now be described. During normal operation of reactor 15, valve 615 is in a closed position, which substantially blocks the flow of steam moderator from the steam area 110 of the reflective zone 95 into a reservoir 625 through passage 610. When controller 540 controls the valve 615 to open, the steam moderator flows from the steam area 110 into a reservoir 625 through the passage 610. After entering the reservoir 625 through the passage 610, the steam moderator condenses on relatively cold surfaces of the interior walls of the reservoir 625 Valve 615 can be opened when a quick shutdown of the reactor is desired. The steam moderator flowing through passage 610 also flows into condenser 635 through passage 630. Due to the heat exchange with relatively cold water (H2O) flowing through passage 80, the steam moderator disposed in condenser 635 condenses into a moderator. liquid. Pump 645 selectively pressurizes a flow of liquid moderator in passages 640 and 650, thereby pumping the condensed liquid moderator back into reactor 15, for example, in the steam area 110. The condensed liquid moderator transferred in the steam area 110 through of passage 650 causes the additional steam moderator in the steam area 110 to condense and reduces a temperature of the moderator in the reflective zone 95. The 645 pump can be operated at a flow rate that maintains a constant vapor pressure in the steam area 110 and in the reflective zone 95. This function is also served by the steam pressure control valve 380b shown in Figure 12N.
[00199] Thus, the moderator stabilization subsystem 525 operates to condense the excess steam moderator and pump it back into the water mirror 105 when a pressure from the steam moderator in the steam area 110 rises above a desired value. Maintaining the steam moderator pressure in the steam area 110 in a desired pressure range provides normal operation of the control cavities 140, 140 ', 140a and / or 140b due to the moderator stabilization subsystem 525 operating to maintain stability of the vapor pressure in the vapor zone 110, to maintain the stability of a temperature of the vapor moderator near the limit 115 of the reflective zone 95 and to maintain the stability of a temperature of the liquid moderator near the limit 115 of the reflective zone 95.
[00200] An exemplary operation of the 530 reactor refrigerant stabilization subsystem will be described now. The substantially free passage of the reactor refrigerant between the reservoir 655 and the passage of the hot reactor refrigerant 325 occurs through a passage 665. The heating element 660 selectively heats the reservoir 655 to keep the reactor refrigerant stored inside the reservoir 655 a a desired temperature and / or pressure when the pressure drops below the desired value. When the pressure rises above a desired value, the cold reactor refrigerant from the cold reactor refrigerant passage 320 is selectively injected into reservoir 655 by a pump (not shown). The relatively cold reactor refrigerant vaporized in reservoir 655 condenses a portion of the reactor refrigerant vapor in reservoir 655, which thereby selectively reduces a pressure in reservoir 655 and the passage of hot reactor refrigerant 325.
[00201] With reference to Figures 15 and 20, an exemplary operation of differential flow subsystem 535 will now be described. Because portions of each area (for example, area A1, A2, A3 and / or A4) at the entry and exit ends of each successive concentric passage 670 can be blocked, a substantially equal flow rate in each of the concentric passages 670 it is maintained through the cold reactor refrigerant passage portions 320 in which concentric passages 670 are arranged. Therefore, because the areas of the concentric passages can vary, the time for the fluid to pass through the different concentric passages can vary and rapid temperature changes in the cold reactor refrigerant passage 320 are spread over time.
[00202] The nuclear reactor system 5 can operate over any suitable period of time, for example, a period of years or decades of continuous operation. As the nuclear reactor system operates over that period of years or decades, a size of gaseous zones 185, 185 ', 185a, 185b, 280 and / or 185b will gradually decrease and substantially disappear towards the end of the time period. operation. Gaseous zones 185, 185 ', 185a, 185b, 280 and / or 185b will be reduced and eventually substantially disappear due to an amount of fuel content in the fuel pipes 135, 135', 135a and / or 135b decreasing over the time and, therefore, a higher moderator density in the control cavity arrangements 130, 130 ', 130a and / or 130b will be used to compensate for the decreased fissile content and to maintain a desired fission ratio. Gaseous zones 185, 185 ', 185a, 185b, 280 and / or 185b will also decrease and eventually substantially disappear due to neutron absorbing fission by-products continuing to accumulate over the period of operation of the nuclear reactor system 5. Consequently, gaseous zones 185, 185 ', 185a, 185b, 280 and / or 185b will also decrease and eventually substantially disappear due to the increase in neutron-absorbing fission by-products over time and, therefore, a greater moderator density in control cavity 130, 130 ', 130a and / or 130b will also be used to compensate for the increased neutron capture and to maintain a desired fission rate.
[00203] Over time, after gaseous zones 185, 185 ', 185a, 185b, 280 and / or 185b have substantially disappeared, an amount of fissile content of the fuel in the fuel pipes 135, 135', 135a and / or 135b may eventually become low enough and / or a number of neutron-absorbing fission by-products produced in reactor 15 will eventually become large enough so that reactor 15 becomes subcritical and the rate of fission in the nuclear reactor system 5 can become insignificant. Therefore, reactor 15 will shut down. At that point, a new fuel can be supplied to reactor 15 or reactor 15 can be operated for brief periods after shutdown following the xenon decay.
[00204] Nuclear reactor system 5 can also be shut down, if desired, before shutdown at the end of the operating time period described above. The nuclear reactor system can be intentionally shut down by the reactor control subsystem 40. In the case of intentional shutdown, the operation of the reactor refrigerant subsystem 25 can be controlled to supply a relatively small amount or substantially no reactor refrigerant and / or refrigerant moderator for reactor 15. In this case, the moderator in control cavity arrangements 130, 130 ', 130a and / or 130b will become very hot, which makes the gas zones 185, 185', 185a, 185b, 280, and / or 185b expand to substantially fill all control cavities 140, 140 ', 140a and / or 140b. As described above, when gas zones 185, 185 ', 185a, 185b, 280 and / or 185b substantially fill all control cavities 140, 140', 140a and / or 140b, the average moderator density in cavity arrangements of control 130, 130 ', 130a and / or 130b decreases. This decrease in moderator density increases the percentage of neutrons lost through absorption at intermediate and high speeds (resonance capture), which therefore decreases the percentage of slow neutrons available to cause fission, which decreases the reactor's heating rate 15 Consequently, if the coolant flow from the reactor and refrigerant moderator to the reactor 15 remains small or substantially stopped, the gas zones 185, 185 ', 185a, 185b, 280 and / or 185b will continue to fill substantially all the control cavities 140 , 140 ', 140a and / or 140b and reactor 15 will shut down. Similar to intentional shutdown, if the reactor refrigerant subsystem 25 does not operate properly and does not provide reactor refrigerant and / or refrigerant moderator for reactor 15, the gas zones 185, 185 ', 185a, 185b, 280 and / or 185b will expand to fill substantially all control cavities 140, 140 ', 140a and / or 140b and reactor 15 will eventually shut down on its own in the same manner as described above for intentional shutdown.
[00205] The operation of the auxiliary refrigerant subsystem 35 will now be described, starting with the description of an exemplary operation of the convection circuit subsystem 410.
[00206] Referring to Figure 16, junctions 425 and 455 can be configured in such a way that, in the substantially total refrigerant flow (total energy operation), pressure A in passage 430 and pressure B at junction 455 oppose and balance each other so that there is substantially no fluid flow through passages 430, 435, 440 and 445, fusion portion 450 and junction 455. If the cooling pump 390 stops pumping cool reactor refrigerant through the passage of cold reactor refrigerant 320, through the reactor core 100, 100 ', 100a and / or 100b and out of the hot reactor refrigerant passage 325 to the heat exchanger 20, then the hot reactor refrigerant leaving the core from reactor 100, 100 ', 100a and / or 100b can flow through passage 430 of convection circuit subsystem 410 at junction 425. Hot reactor refrigerant flows down through passage 430, below an elevation of the top surface of the water mirror 105. The hot reactor refrigerant then flows up from passage 430 into passage 435 and then towards detention structure 85 and pressure vessel 90 through the plurality of passages 440. hot reactor refrigerant flows from the plurality of passages 440 in the corresponding plurality of passages 445. The hot reactor refrigerant flows through the plurality of passages 445, which gives heat by exchanging heat to the pressure vessel 90. The reactor refrigerant flows through the plurality of passages 445 to a close position or below the bottom of the reactor core 100, 100 ', 100a and / or 100b. The reactor refrigerant then flows into the cold reactor refrigerant passage 320 through junction 455. The reactor refrigerant that enters the cold reactor refrigerant passage 320 then enters the reactor core 100, 100 ', 100a and / or 100b. After leaving the reactor core 100, 100 ', 100a and / or 100b, part of the reactor refrigerant re-enters the convection circuit subsystem 410 at junction 425.
[00207] Pressure A opposes and balances pressure B when pump 390 circulates the cold refrigerant moderator at a rate that corresponds to the operation at the maximum power of the reactor so that very little refrigerant flows through the convection circuit at full power. At less than full power (which can be at a much lower reactor refrigerant flow than or substantially no reactor refrigerant flow), a convection circuit operates to circulate reactor refrigerant through the 410 convection circuit subsystem Therefore, if desired, the convection circuit subsystem 410 operates to circulate reactor refrigerant through reactor 15 even when reactor refrigerant subsystem 25 is not in operation. The convection circuit subsystem 410 and valves 460 and 465 can be autonomous systems that operate independently of the 540 controller and any source of electrical power. For example, valves 460 and 465 can operate to isolate a reactor refrigerant flow within the convection circuit subsystem 410 in the event of a flow interruption in the reactor refrigerant subsystem 25 or a leak in any of the components of the subsystem refrigerant flow outside holding structure 85. Valve 460 operates to substantially block a flow of reactor refrigerant outside reactor 15 through the cold reactor refrigerant passage 320 in any case when the external pressure is less than the pressure in the reactor passage. cold reactor refrigerant 320 inside pressure vessel 90. In addition, valve 465 operates to substantially block the flow of reactor refrigerant outside reactor 15, when a quantity of reactor refrigerant in reactor 15 is less than a desired limit quantity . Therefore, the convection circuit subsystem 410 operates to maintain the reactor refrigerant circulation through the reactor 15 independently of an operation of the reactor refrigerant subsystem 25 if desired.
[00208] With reference to Figures 17 and 18, an exemplary operation of the auxiliary heat exchange subsystem 415 will now be described. When the temperature of the moderator within the reflective zone 95 exceeds its normal operating temperature, the pressure vessel 90 is also heated to about the same temperature by the conduction of the moderator and the moderator vapor. The changing material housed within the heat exchange member 470 is heated in an increasing manner. If heated beyond a threshold level, the changing material disposed on the heat exchange members 470 will change state (for example, heated from a solid state to a liquid state or heated from a liquid state to a gaseous state ), which improves the conductivity properties of the changing material disposed in the heat exchange members 470. The changing material material of the heat exchange member 470 will effectively transfer heat out of the pressure vessel 90 by convection or by steam transfer and towards an exterior of the detention structure 85, which may have a low thermal conductivity.
[00209] The material in change of state of the heat exchange member 475 is then heated by the heat transferred from the heat exchange member 470. If heated beyond a threshold level, the material in change of state arranged in the members heat exchanger 475 will change states (for example, heated from a solid state to a liquid state or heated from a liquid state to a gaseous state), which improves the conductivity properties of the material changing state disposed on members heat exchanger 475.
[00210] The changing state material of heat exchange members 475 will then flow from heat exchange member 475 into heat exchange member 480. When heat exchange members 480 extend over a wide area of terrain (eg, field and / or parking), the heat transferred by the material in a changing state of disposition and / or flowing in the heat exchange members 480 will dissipate in the adjacent terrain and on the surface of the soil. In addition, when the heat exchange members 480 are disposed at a slightly upward angle to a substantially horizontal plane, the material in a changing state arranged and / or flowing within the heat exchange member 480 increasingly dissipates the heat as the distance from reactor 15 increases.
[00211] When cooled beyond the threshold level, the changing material disposed in the heat exchange members 480 will change states again (for example, cooled from a gaseous state in a liquid state or cooled from a liquid state in a solid state). For example, if the changing material in the heat exchanger members 475 and 480 is H2O, the vapor (H2O) condenses into water (H2O). When the heat exchange members 480 are arranged at a slightly upward angle from a substantially horizontal plane, the changing material, for example, water (H2O), will form vapor bubbles in the heat exchange members 475 that rise rapidly to the top of the heat exchanger members 475 and then flow out along the tops of the heat exchange members 480 until they condense in the cooler water (H2O) on the heat exchange members 480 and flow because of gravity towards reactor 15. As the changing material flows back through the heat exchanging members 480 due to gravity towards the reactor 15 and the heat exchanging members 475, the changing material of state becomes increasingly heated again. If heated beyond a threshold level, the changing material disposed on the heat exchange members 475 will change states (for example, heated from a liquid state to a gaseous state or heated from a solid state to a liquid state ). The changing material can be heated and cooled iteratively, thus changing between states in a cycle and continuously transferring heat out of the reactor 15 to be dissipated over the wide area of land (for example, field and / or parking) under which the heat exchange members 480 extend. It is contemplated that in addition to operating within the nuclear reactor system 5, the auxiliary heat exchange subsystem 415 can be used in conjunction with any suitable heat transfer application in which the heat is transferred out of a central source (for example , any type of power plant, any type of heat production structures such as commercial buildings, military applications, residential complexes and / or sports complexes).
[00212] With reference to Figure 19, an exemplary operation of the auxiliary reactor shutdown subsystem 420 will now be described. During normal operation of reactor 15, valve 487 may remain closed. When an influx of neutron absorbing material into reactor 15 is desired (for example, when a shutdown of reactor 15 is desired), controller 540 controls valve 487 to open to allow the flow of pressurized neutron absorbing material from the pressurized reservoir 485 in one or more passages 490. The neutron absorbent material flows through one or more passages 490, which thus flows through the reactor core 100, 100 ', 100a and / or 100b. As the neutron absorbent material flows towards the end portion 505, the vapor (H2O) previously disposed in passage 490 becomes increasingly pressurized in the closed end portion 505 that serves as a plug and reduces the possibility of material flow neutron absorber escaping from the end portion 505 due to the pressurized flow force of the pressurized reservoir 485 in passage 490. Due to the presence of neutron absorbing material in passages 490, an increasing amount of neutrons is absorbed from reactor 15, which decreases the reactor fission rate 15. Controller 540 controls pump 500 to pump neutron absorbing material from passage 490 back into reservoir 485 through drain passage 495 when it is desired to restart the reactor. When substantially no neutron absorbing material is desired in passage 490, controller 540 controls valve 487 to close substantially completely and controls pump 500 to evacuate neutron absorbing material from passage 490 in pressurized reservoir 485. Pump 500 maintains the reservoir pressurized 485 in a pressurized state and the process described above can be repeated as desired.
[00213] The revealed nuclear reactor system can be used to make control of a nuclear reactor easier. For example, reactor 15 can be built without moving parts within the containment structure 85. The revealed control method has a relatively wide range (for example, above 250 mk), which allows the use of fuels that have widely reactivities while obtaining a substantially maximum conversion ratio for each different fuel at substantially all points in the fuel life cycle. The revealed nuclear reactor system also greatly increases the conversion ratio and therefore increases the life of the fuel. In addition, due to the relatively wide range of the revealed control method, reactor 15 can use more reactive fuels such as low enriched uranium, MOX fuel, used reactor light water fuel and fuel combinations that include thorium .
[00214] Because the revealed control cavities react independently to control the local neutron flow, xenon waves can be suppressed naturally, which increases the efficiency of the reactor 15. In addition, the neutron flow through the nucleus of the reactor 100, 100 ', 100a and / or 100b is well leveled, which allows a relatively greater total energy output from the nuclear reactor system 5. In addition, the burning of fuel by the reactor core 100, 100', 100a and / or 100b can be relatively balanced.
[00215] The revealed nuclear reactor system may not have to use continuous or partial refueling due to the excess of neutrons being used to extend the life of the higher conversion ratio of fresh fuel, instead of being used to extend less effectively the oldest fuel life which has a lower conversion rate. Because the reactor 15 can use natural uranium as fuel, the reactor 15 cannot use the isotope enrichment capacity (for example, uranium), therefore, reducing the possibility of nuclear proliferation. Due to the high conversion rate of reactor 15, a large part of the energy output is produced by fission of plutonium isotopes (mostly Pu239) produced from U238 in reactor 15, which, therefore, significantly increases the total KWH of power produced per ton of uranium extracted and which significantly decreases the amount of nuclear waste generated by KWH of power produced.
[00216] The revealed control cavities can provide the reactor 15 with a simple structure for effective control of the nuclear reactor system 5. The revealed control cavities can provide a reduced temperature difference between the reactor refrigerant and the moderator so that the heat loss of the hot refrigerant to the moderator is reduced, which allows for higher outlet refrigerant temperatures and more efficient steam turbines. In addition, the revealed control cavities can provide a reduced pressure difference by the reactor 15, which allows the refrigerant pressure tubes to be made with less structural material, which absorbs less neutrons and can increase the fuel conversion ratio .
[00217] Revealed fuel assemblies can provide inner fuel rods in the revealed fuel tubes that are relatively less shaded from thermal neutrons by external fuel rods so that temperatures are relatively equal across the fuel tubes, which allows fuel pipes and fuel assemblies contain more fuel rods and / or larger diameter fuel rods. Consequently, the energy output per volume of the reactor can be increased.
[00218] The auxiliary heat exchange system 415 can provide a method for effective heat transfer from reactor 15 or any other suitable heat source. The auxiliary heat exchange system 415 provides an effective heat transfer system that can operate without moving mechanical parts.
[00219] The revealed nuclear reactor system can also provide automatic and / or intentional shutdown of reactor 15 when desired. The disclosed reactor system can also provide methods for controlling an amount of steam that is delivered to the turbine 45 through a bypass system, which can take control of power production more effectively.
[00220] It will be apparent to those skilled in the art that various modifications and variations can be made to the revealed nuclear reactor system. Other modalities will be apparent to those skilled in the art from the consideration of the specification and the practice of the revealed method and apparatus. It is intended that the report described and the examples are considered only as examples with a true scope being indicated by the following claims and equivalents thereof.

权利要求:
Claims (20)
[0001]
1. A method for controlling a nuclear reactor, comprising: providing a reactor core that includes a fuel assembly, the fuel assembly including a plurality of fuel elements; provide a reflective zone that surrounds the reactor core; characterized by comprising: providing a plurality of adjacent boxes, each having a cavity, adjacent to the fuel elements; allowing the movement of a moderator inside and outside each cavity of the plurality of adjacent boxes in a lower part of the plurality of adjacent boxes; and confining the moderator in each cavity of the plurality of adjacent boxes in an upper part of the plurality of adjacent boxes; wherein the moderator moves from at least one of the plurality of adjacent boxes to the reflecting zone through the bottom of at least one of the plurality of adjacent boxes, and the moderator moves from the reflecting zone to at least one of the plurality of adjacent boxes across the bottom of at least one of the plurality of adjacent boxes.
[0002]
2. Method according to claim 1, characterized by the moderator being D2O.
[0003]
3. A method for controlling a nuclear reactor, comprising: providing a reactor core that includes a fuel assembly, the fuel assembly including a plurality of fuel elements; provide a reflective zone that surrounds the reactor core; characterized by comprising: providing a plurality of adjacent boxes, adjacent to the fuel elements, each adjacent box having a cavity; allow the movement of a moderator inside and outside each cavity in a lower part of the adjacent box; block a movement of the moderator inside and outside each cavity in an upper part of the adjacent box; maintaining an amount of heat removed from the moderator in each cavity substantially equal to an amount of heat transmitted by heat conduction, neutron radiation or gamma radiation from the fuel set to the moderator in each cavity; and maintaining a substantially constant amount or slowly changing the moderator in a gaseous state in each cavity in an upper part of the adjacent box; wherein the moderator moves from at least one of the plurality of adjacent boxes to the reflecting zone through the bottom of at least one of the plurality of adjacent boxes, and the moderator moves from the reflecting zone to at least one of the plurality of adjacent boxes across the bottom of at least one of the plurality of adjacent boxes.
[0004]
Method according to claim 3, characterized by the moderator being D2O.
[0005]
5. A method for controlling a nuclear reactor, comprising: providing a reactor core that includes a fuel assembly, the fuel assembly including a plurality of fuel elements; provide a reflective zone that surrounds the reactor core; characterized by comprising: providing a plurality of adjacent boxes, adjacent to the fuel elements, each adjacent box having a cavity; allow the movement of a moderator inside and outside each cavity in a lower part of each adjacent box; block a movement of the moderator in a gaseous state outside each cavity in an upper part of each adjacent box; remove a quantity of heat from the moderator in each cavity; and controlling an amount of moderator that is maintained in a gaseous state in each cavity at the top of each adjacent box by varying the amount of heat removed from the moderator in each cavity; wherein the moderator moves from at least one of the plurality of adjacent boxes to the reflecting zone through the bottom of at least one of the plurality of adjacent boxes, and the moderator moves from the reflecting zone to at least one of the plurality of adjacent boxes across the bottom of at least one of the plurality of adjacent boxes.
[0006]
6. Method according to claim 5, characterized by the moderator being D2O.
[0007]
7. A method for controlling a reaction rate for a nuclear reactor core, comprising: providing a reactor core that includes a fuel assembly, the fuel assembly including a plurality of fuel elements; provide a reflective zone that surrounds the reactor core; characterized by comprising: providing a plurality of adjacent boxes, adjacent to the fuel elements, each adjacent box having a cavity; allow the movement of a moderator inside and outside each cavity; using neutron radiation or gamma radiation released from fuel elements to heat a part of the moderator in each cavity in a gaseous state, each plurality of adjacent boxes having a closed upper part and an open lower part; retain the moderator in the gaseous state in each cavity in each closed upper part; varying an amount of moderator in each cavity, maintained in a gaseous state by varying the amount of heat removed from the moderator in each cavity; and varying the amount of neutrons captured by the resonance-captured fuel assembly by moving a part of the moderator in each cavity to a liquid state based on the amount of moderator in each cavity maintained in the gaseous state; wherein the moderator moves from at least one of the plurality of adjacent boxes to the reflecting zone through the open bottom of at least one of the plurality of adjacent boxes, and the moderator moves from the reflecting zone to at least one the plurality of adjacent boxes through the open bottom of at least one of the plurality of adjacent boxes.
[0008]
8. Method according to claim 7, characterized by the moderator being D2O.
[0009]
9. Method, according to claim 7, characterized by, when the reaction rate is greater than a desired value, the higher reaction rate increases the neutron flow in each cavity, increases the heat deposition inside the moderator in each cavity, increase the amount of moderator in each cavity in the gaseous state and move part of the moderator in the liquid state in each cavity descending out of each respective cavity, which decreases the mass of the moderator in each cavity, increases an amount of captured neutrons by resonance capture and decreases the amount of neutrons that reach thermal energy and cause fission.
[0010]
10. Method according to claim 7, characterized by, when the reaction rate is below a desired value, the lower reaction rate decreases the neutron flow in each cavity, decreases the heat deposition inside the moderator in each cavity, increase the condensation rate of the gas moderator in each cavity to the liquid state, decrease the amount of moderator in each cavity in the gas state and allow the displacement of part of the liquid moderator in the moderator zone upwardly into the respective cavity, which increases the mass of the moderator in each cavity, decreases the amount of neutrons captured by resonance capture and increases the amount of neutrons that reach thermal energy and cause fission.
[0011]
11. An apparatus for a nuclear reactor, comprising: a containment structure, with the following being disposed in the containment structure: a reactor core that includes a fuel assembly, the fuel assembly including a plurality of fuel elements; a reflective zone that surrounds the reactor core; characterized by understanding: neutron moderating material, in which at least part of the neutron moderating material is a fluid and the fluid neutron moderating material is disposed both in the reactor core and in the reflecting zone; and a plurality of adjacent boxes arranged adjacent to the fuel elements, each adjacent box having a cavity and wherein a lower part of each adjacent box is opened for movement of the fluid neutron moderating material inside and outside the cavity and an upper part each adjacent box is closed for movement of the fluid neutron moderating material inside or outside the upper part of the cavity; wherein the fluid neutron moderation material moves from at least one of the plurality of adjacent boxes to the reflecting zone through the bottom of at least one of the plurality of adjacent boxes, and the fluid neutron moderation material moves from the reflective zone to at least one of the plurality of adjacent boxes through the bottom of at least one of the plurality of adjacent boxes.
[0012]
Apparatus according to claim 11, characterized by at least part of the neutron moderating material being in a liquid state and at least part of the neutron moderating material being in a gaseous state in both the reflecting zone and at least some of the cavities.
[0013]
13. Apparatus according to claim 11, characterized by the neutron moderating material fluid disposed in the cavities being heavy water (D2O).
[0014]
Apparatus according to claim 11, characterized by the fluid neutron moderating material disposed in the cavities being light water (H2O).
[0015]
Apparatus according to claim 11, characterized in that the fuel elements are substantially vertical structures and one or more cavities surround the fuel elements and substantially fill a plurality of spaces between the fuel elements.
[0016]
Apparatus according to claim 11, characterized by additionally including a cooling assembly that includes a tube that passes through a bottom part of at least one adjacent box, the tube including one or more openings configured to allow moderation material relatively cooler neutron fluid to flow into the cavity of at least one adjacent box to mix with the fluid neutron moderating material already disposed in the cavity.
[0017]
Apparatus according to claim 16, characterized by, when there are a plurality of adjacent boxes stacked vertically around each fuel element, the tube passes through a top part of at least one adjacent box which is not the most high of the adjacent boxes stacked vertically, the tube being sealed in an upper part of at least one adjacent box and blocking the movement of the gaseous neutron moderating material from the top of at least one adjacent box.
[0018]
Apparatus according to claim 16, characterized in that the plurality of adjacent boxes is stacked substantially vertically and surrounds part or all of at least one substantially vertical fuel element.
[0019]
Apparatus according to claim 18, characterized by the tube passing through more than one of the adjacent boxes of the substantially vertical stack, an upper end part of the tube being arranged below a top part of the highest adjacent box.
[0020]
20. Apparatus according to claim 11, characterized by the fluid neutron moderating material that moves from at least one of the plurality of adjacent boxes to the reflecting zone through the bottom of at least one of the plurality of adjacent boxes. a liquid, and the fluid neutron moderating material that moves from the reflective zone to at least one of the plurality of adjacent boxes through the bottom of at least one of the plurality of adjacent boxes is a liquid.

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同族专利:

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公开号 | 公开日

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CA2823960C|2014-08-05|

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JP2014510284A|2014-04-24|

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CN103348413B|2016-01-13|

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CN103348413A|2013-10-09|

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EP2707881B1|2018-04-25|

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EP2707881A4|2015-02-25|

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US8416908B2|2013-04-09|

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WO2012158459A1|2012-11-22|

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MX2013013269A|2013-12-06|

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EP2707881A1|2014-03-19|

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US20130301773A1|2013-11-14|

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JP5608832B2|2014-10-15|

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KR101412520B1|2014-06-26|

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KR20130136533A|2013-12-12|

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CA2823960A1|2012-11-22|

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RU2532540C1|2014-11-10|

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BR112013029172A2|2017-01-31|

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ES2677101T3|2018-07-30|

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US20120288048A1|2012-11-15|

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法律状态:
2018-12-11| B06F| Objections, documents and/or translations needed after an examination request according [chapter 6.6 patent gazette]|

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2020-01-28| B06U| Preliminary requirement: requests with searches performed by other patent offices: procedure suspended [chapter 6.21 patent gazette]|

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2020-06-02| B09A| Decision: intention to grant [chapter 9.1 patent gazette]|

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2020-10-13| B16A| Patent or certificate of addition of invention granted|Free format text: PRAZO DE VALIDADE: 20 (VINTE) ANOS CONTADOS A PARTIR DE 10/05/2012, OBSERVADAS AS CONDICOES LEGAIS. |

优先权:

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申请号 | 申请日 | 专利标题

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US201161485656P| true| 2011-05-13|2011-05-13|

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US61/485,656|2011-05-13|

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PCT/US2012/037314|WO2012158459A1|2011-05-13|2012-05-10|Nuclear reactor control method and apparatus|

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