• 专利附录
  • 专利说明
  • 权利要求
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    • 专利摘要:
    A nuclear device comprising: a heat pipe (3); a first fuel (15) positioned around a lateral surface of the heat pipe parallel to a central axis of the heat pipe, the first fuel containing a fissile material at a first concentration; a second fuel (16) positioned on an outer side of the first fuel and containing fissile material at a second concentration lower than the first concentration; and a core (32) having a plurality of heat pipes arranged parallel to each central axis in the first fuel or in the first fuel and the second fuel.
    公开号:FR3054715A1
    申请号:FR1757158
    申请日:2017-07-27
    公开日:2018-02-02
    发明作者:Rei KIMURA；Taishi Yoshida；Satoshi Wada；Yoshiro NISHIOKA；Yoshihiro HYODO；Kunio Hoshino；Ryosuke Miura
    申请人:Toshiba Corp；
    IPC主号:
    专利说明:

    Holder (s): KABUSHIKI KAISHA TOSHIBA.
    Extension request (s)
    Agent (s): CABINET FEDIT LORIOT.
    p4) NUCLEAR REACTOR AND METHOD FOR TRANSFERRING HEAT FROM A HEART.
    FR 3 054 715 - A1
    16 /) A nuclear device, comprising: a heat pipe (3); a first fuel (15) positioned around a lateral surface of the heat pipe parallel to a central axis of the heat pipe, the first fuel containing a fissile material at a first concentration; a second fuel (16) positioned on an outer side of the first fuel and containing fissile material at a second concentration lower than the first concentration; and a core (32) comprising a plurality of heat pipes arranged parallel to each central axis in the first fuel or in the first fuel and the second fuel.

    NUCLEAR REACTOR AND METHOD FOR TRANSFERRING HEAT FROM A HEART
    In the field of the invention, embodiments relate to a small nuclear reactor used, for example, in space, on the Moon and in polar regions of the earth.
    In the prior art, small nuclear reactors produce more energy per unit of weight than other types of nuclear reactors. Small reactors have, for example, been used as energy sources in space. Small nuclear reactors have heat pipes that transmit heat produced in the reactor core to other parts of the reactor. Heat pipes transmit a large amount of heat per unit volume and do not require moving components. The heat pipes with such a simple structure have ensured the simplification of small nuclear reactors. Heat pipes without moving components do not induce the problems related to moving components. Such heat pipes have improved the reliability of small nuclear reactors. In small nuclear reactors, a plurality of heat pipes with a small diameter can be positioned in the cores.
    In summary, the present embodiments describe a nuclear reactor comprising a heat pipe, a first fuel positioned around a lateral surface of the heat pipe parallel to a central axis of the heat pipe, the first fuel containing a fissile material at a first concentration, a second fuel positioned on an external face of the first fuel and
    -2 containing a fissile material at a second concentration lower than the first concentration and a core comprising a plurality of heat pipes arranged parallel to each central axis in the first fuel or in the first fuel and the second fuel.
    Preferably, a concentration of the fissile material in a first zone is higher than that in a second zone and the heat transferred to the heat pipes from the second zone is lower than the heat transferred to the heat pipes from the first zone.
    Preferably, the first zone contains more heat pipes than the second zone per unit area on a cross section of the heart perpendicular to the central axis of the heat pipe.
    The nuclear reactor may further comprise: a first layer which includes the plurality of heat pipes parallel to their central axes, the second fuel being around the first fuel around each of the heat pipes close to each other; a first heat conductor along a lateral surface of the first layer and parallel to the central axis, the thermal conductivity of the first heat conductor being greater than that of the second fuel.
    Preferably, the first heat conductor contains beryllium.
    The nuclear reactor may further comprise: a layer which includes the plurality of heat pipes in parallel with the central axes, the second fuel being around the first fuel around each of the heat pipes close to each other; and a second heat conductor positioned in the second fuel.
    The nuclear reactor may further comprise: a layer which includes the plurality of heat pipes in parallel with the central axes, the second fuel being around the first fuel around each of the heat pipes close to each other; and a heat conductor connecting two overlapping layers, wherein a first end of the heat conductor is closer to the heat pipe than a second end.
    The nuclear reactor can also comprise: a first layer which
    -3 has the plurality of heat pipes in parallel with the central axes, the second fuel being around the first fuel around each of the heat pipes close to each other; a second layer which comprises the plurality of heat pipes in parallel with the central axes, the second fuel being around the first fuel around each of the heat pipes close to each other and covering the first layer; wherein a heat pipe of the second layer is positioned between two heat pipes close to each other in the first layer.
    The nuclear reactor may further comprise: a metal layer between the heat pipe and the first fuel, comprising a metal, in which a temperature of the melting point of the metal is higher than a temperature before a start-up operation of the nuclear reactor and n is not higher than an operating temperature of the nuclear reactor.
    Preferably, the core comprises a plurality of cylinders arranged concentrically, in which each of the cylinders is produced in a layer comprising the plurality of heat pipes in parallel with the central axes, the first fuel and the second fuel around the first fuel around each heat pipes close to each other.
    Preferably, the content of fissile material in the core differs along the axis of the heat pipe.
    Preferably, the core is divided into multiple sections in the direction of the central axis of the core, in which a concentration of fissile material in each section is adjusted according to a position of the section.
    Preferably, a point producing maximum heat in one layer does not overlap a point producing maximum heat in a next adjacent layer.
    Preferably, the content of the fissile material in the core differs in a radial direction over a cross section of the core perpendicular to the central axis of the heat pipe.
    The nuclear reactor may further comprise: a control rod arranged on a central axis of the core, in which the content of the fissile material in
    -4the central part of the heart, near a lateral surface of the heart parallel to a central axis of the heart, and that near a midpoint of a length of the heart parallel to the central axis, are less than those other parts in the heart.
    The present invention further relates to a method of transferring heat from the interior of a nuclear reactor core to the exterior of the core, comprising: the transfer of heat produced in a first fuel to a heat pipe positioned in the first fuel, the first fuel containing a fissile material at a first concentration; transferring heat produced in a second fuel positioned on an external side of the first fuel into the heat pipe by the first fuel, the second fuel containing the fissile material at a second concentration lower than the first concentration; and transferring the heat produced in the first fuel and the second fuel outside the core.
    A brief description of the drawings will then be given. A more complete appreciation of embodiments and many of their own advantages will be easily acquired when these are better understood by referring to the following detailed description considered in relation to the appended drawings, among which:
    Figure 1 is a schematic view of a nuclear power generator of a first embodiment;
    Figure 2 is a schematic view of a heat pipe of the first embodiment;
    FIG. 3 is a schematic view showing an arrangement of nuclear fuels described in the first embodiment;
    Fig. 4 is a schematic view showing an arrangement of nuclear fuels on a core in one embodiment;
    Figure 5 is a schematic view showing first heat conductors in one embodiment;
    Figure 6 is a schematic view showing second conductors
    -5 heat and third heat conductors in one embodiment;
    Figure 7 is a schematic cross-sectional view of a nuclear reactor in one embodiment;
    Figure 8 is an enlarged schematic cross-sectional view of a nuclear reactor in one embodiment;
    Figure 9 is a schematic cross-sectional view of a nuclear reactor in one embodiment, showing an arrangement of nuclear fuels in a nuclear reactor;
    Fig. 10 is a schematic view showing the concentration of fissile material in a first fuel of each section in one embodiment;
    FIG. 11 is a schematic view showing the concentration of fissile material in a second fuel of each section in one embodiment;
    Fig. 12 is a schematic view showing the amount of energy produced by the first fuel in each section in one embodiment;
    Fig. 13 is a schematic view showing the amount of energy produced by the second fuel in each section in one embodiment;
    Fig. 14 is a schematic view showing the amount of energy produced by the first fuel in each section assuming that the content of the first fuel in each section is equal in one embodiment;
    Fig. 15 is a schematic view showing the amount of energy produced by the second fuel in each section assuming that the content of the second fuel in each section is equal in one embodiment;
    FIG. 16 is an algorithm of a heat transfer method from the interior of a core of a nuclear reactor to the exterior of the core in one embodiment.
    A detailed description of preferred embodiments will now be given below with reference to the drawings. A general view of a small nuclear reactor is described with reference to Figures 1 and 2. The small nuclear reactor 1 shown in Figure 1 is a small nuclear reactor used as an energy generator, for example, in the space, on the Moon, on Mars, in polar regions on the earth, etc ...
    In a small nuclear reactor, the highest acceptable temperature in a core is predetermined based on the heat resistance of the reactor structure. For example, in a small nuclear reactor with a metal hydride, the highest acceptable temperature in a core is lower than the hydrogen dissociation temperature to prevent the dissociation of hydrogen. The heat produced near the heat pipes is easily transferred to the heat pipes and contributes to the energy produced by the reactor. On the other hand, the heat produced relatively far from the heat pipes is more difficult to transfer to the heat pipes and contributes less to the energy produced by the reactor. As a result, the temperature farther from the heat pipes in the heart is higher than that at other parts of the heart near the heat pipes. To keep the temperature at distant parts of the heat pipes lower than the predetermined temperature, the temperature of the whole heart must be reduced. This means that the energy delivered by the reactor has been limited in order to keep the temperature away from the heat pipe at a cooler value than the predetermined temperature.
    In the device based on a small nuclear reactor 1 described in this embodiment, a rise in the local temperature is prevented and the energy produced by the reactor is increased.
    As shown in FIG. 1, the device based on a small nuclear reactor 1 comprises a nuclear reactor 2 containing nuclear fuel, a plurality of heat pipes 3 transferring the heat produced by fission of the nuclear fuel in the nuclear reactor 2 to the outside of nuclear reactor 2, a shield 4 blocking radiation from inside the nuclear reactor 2, an energy production section 5 converting heat
    - 7transmitted through the heat pipes 3 into electricity and a plurality of radiators 6 dissipating the remaining heat from the energy production section 5.
    In a device based on a small nuclear reactor 1 intended for use in space, the shield 4 can be arranged between the nuclear reactor 2 and the power generation section 5, and thus, the radiation from the nuclear reactor 2 n '' reach any component behind shield 4 from the nuclear reactor
    2. The arrangement of the shield 4 is not just limited between the nuclear reactor 2 and the power generation section 5. In a device based on a small nuclear reactor 1 intended for use on earth, the shield 4 can alternatively cover the entire circumference of nuclear reactor 2.
    The nuclear reactor 2 further comprises, for example, a container 7 covering the nuclear fuel and the heat pipes 3, and a moderator (not shown) ensuring the deceleration of the neutrons and a control bar controlling the fission reaction. The container 7 may include a neutron reflector reflecting the neutrons emitted by the nuclear fuel. A structure comprising nuclear fuel, the heat pipes 3, the moderator, the control bar and the container 7 can be called a core 32. The heat pipes
    3, as a mechanism for removing heat, are contained in the core 32. The function of the core 32 is identical to that of the reactor 2. A shape of the nuclear reactor 2 and of the core 32 is not limited to a cylinder . In certain embodiments, the shape of the nuclear reactor 2 and of the core 32 is, for example, cylindrical, rectangular or conical. The core 32 comprises a plurality of heat pipes 3 arranged parallel to each central axis of the fuel containing fissile material.
    The energy production section 5 includes thermoelectric conversion elements intended to convert the heat transmitted through the heat pipes 3 into electricity. The thermoelectric conversion elements produce electricity by the temperature differences occurring inside.
    The power generation section 5 is not limited to generating electricity with thermoelectric conversion elements. The power generation section 5 can convert heat into electricity with, for example,
    -8 turbines or a Stirling engine. In this case, turbines turn with the steam produced by the heat from the heat pipes 3 and produce electricity. The Stirling engine is driven by a change in the volume of gas sealed in the Stirling engine and produces electricity.
    As shown in FIG. 2, showing one of the heat pipes 3, a heat transfer fluid transfers heat into the heat pipe 3. The heat pipe 3 comprises a heat pipe cover 8 made from materials having a high thermal conductivity, a volatile liquid as heat transfer fluid being sealed in the heat pipe casing 8, a free space 9 and a wick 10 forming a capillary structure in the inner part of the heat pipe casing 8. The vaporized heat transfer fluid moves in the free space 9. The heat pipe casing 8 and the wick 10 can, for example, be made of aluminum and copper. The heat transfer fluid is, for example, a fluorocarbon substitute.
    The end of the heat pipe 3 is a high temperature section 11 which is intended to be heated from the outside, and the other end of the heat pipe 3 is a low temperature section 12 which is intended to be cooled from the outside. The evaporation cycle at the high temperature section 11 (latent heat absorption) and condensation at the low temperature section 12 (latent heat release) of the heat transfer fluid ensures the transfer of heat in the heat pipe 3 .
    The following is an example of this cycle in the heat pipe 3. The heat transfer fluid is heated in the high temperature section 11. The heat transfer fluid absorbs heat and evaporates into gas 13. The gas 13 moves towards the section at low temperature 12 through the free space 9. The gas 13 is cooled in the low temperature section 12. The gas 13 releases heat and condenses into liquid 14. The liquid 14 at the low temperature section 12 moves to the high temperature section 11 through the wick 10 by capillary action. This cycle is executed even if there is no difference in height between the high temperature section 11 and the low temperature section 12 or even if the heat pipe is in a zero gravity or low gravity state. For example, in space, heat is transferred from the high temperature section 11 to the section at
    -9 low temperature 12 in the heat pipe 3 due to such an evaporation and condensation cycle of the heat transfer fluid and the displacement of the gas 13 and the liquid 14.
    The high temperature sections 11 of the plurality of heat pipes 3 are inserted into the core 32. The low temperature sections 12 of the heat pipes 3 extend linearly from the heart 32 in the reactor 2 to end in the production section of energy 5. The energy production section 5 converts heat into electricity, and the heat produced in the heart 32 is transferred to the energy production section 5 through the heat pipes 3.
    The reactor 2 is described in more detail with reference to FIG. 3. The same configurations as those already described are given the same reference numbers, thus omitting a redundant description.
    Figure 3 is an enlarged cross-sectional view of a cell 20 of the heart 32 perpendicular to the central axis of the heat pipe 3. A direction parallel to the central axis of the heat pipe 3 is called the third direction. In FIG. 3, the internal structures of the heat pipe 3 are omitted from the representation. To facilitate understanding, certain hatches can be omitted on each section view. The fuel 15 and the fuel 16 are arranged around the heat pipe 3. The fuel 15 and the fuel 16 contain fissile material causing a fission reaction and non-fission (or fertile) material causing no fission reaction. The fissile material is, for example, Uranium 235 (U 235). The non-fission material is, for example, Uranium 238 (U 238). The fissile material is not limited to U 235. In certain embodiments, the fissile material can be TU233, Pu239, Pu241, Am 242, Cm 243 and Cm 245. In certain embodiments, the non-fission material can be FU233, Pu239, Pu241, Am 242, Cm 243 and Cm 245. Fuels 15 and 16 can contain different types of materials as the base material , for example, metal, oxide, nitride, carbide, chloride, and fluoride.
    Fuel with a high concentration of fissile material produces a high amount of heat per unit volume by a fission reaction. Fuel 15 contains fissile material at a first concentration. The
    -10combustible 16 contains fissile material at a second concentration. The first concentration is higher than the second concentration. Below, fuel 15 is called the first fuel 15, and fuel 16 is called the second fuel 16.
    According to FIG. 3, the first fuel 15 is positioned around a lateral surface of the heat pipe 3 parallel to the central axis of the heat pipe 3. The second fuel 16 is positioned further from the heat pipe 3 than the first fuel 15. For example, the second fuel 16 is positioned on an external face of the first fuel 15. In FIG. 3, the second fuel 16 is around the first fuel 15. In the core 32, a first zone and a second zone respectively comprise the first fuel 15 and the second fuel 16 in FIG. 3. The concentration of the fissile material in the first zone is higher than that in the second zone. The heat produced in the first zone is more easily transferred by the heat pipes 3 than the heat produced in the second zone. In the core 32 the heat pipes 3 are arranged at regular intervals.
    The shape of the first fuel 15 can be that of a cylinder with a heat pipe 3 as a central axis. The shape of the second fuel 16 can be rectangular, the first fuel 15 being inserted inside. A pair of the first fuel 15 and of the second fuel 16 forms the cell of 20. The heart 32 is formed by a plurality of cells 20 arranged parallel to the heat pipe 3. In a cross-sectional view of the heart 32 perpendicular to the central axis of the heart 32, the limits of cells 20 form a grid.
    The shape of the first fuel 15 and the second fuel 16 is not limited to a cylindrical or rectangular shape. In certain embodiments, the first fuel 15 and the second fuel 16 can be formed in a circle, oblong, triangular, rectangular or hexagonal in a cross-sectional view of the heart 32 perpendicular to the central axis of the heart 32.
    The shape of the heat pipe 3 is not limited to a circular tube. The cross-sectional shape of heat pipe 3 perpendicular to its central axis is not
    - it limited to a circle. In certain embodiments, the cross-sectional shape of the heat pipe 3 perpendicular to its central axis can, for example, be oval, triangular, quadrangular, or hexagonal. Each heat pipe of the plurality of heat pipes 3 is not limited to a single shape. In certain embodiments, the diameter of each heat pipe 3 may be different. In a first heat pipe 3, there may be parts with different diameters.
    During the critical phase, the first fuel 15 produces heat with an energy density greater than that of the second fuel 16. This is due to the fact that the concentration of the fissile material of the first fuel 15 is greater than that of the second fuel 16. The formula (1) is the relationship between the thickness of a plate-shaped heat conductor and the heat conducted by a heat conductor, λ represents the thermal conductivity of the heat conductor. A represents the heat conducting section. ΔΤ represents the temperature difference in the conductor. 1 represents the thickness of the heat conductor, q is the heat conducted by the heat conductor. According to formula (1), ΔΤ and 1 are inversely proportional. By reducing 1, more heat can be transferred even if ΔΤ is limited.
    (1) λΑ & Τ
    In FIG. 3, the thickness of the fuel around the heat pipe 3 in the direction perpendicular to the central axis is 1 of equation (1). The heat produced in the fuel will be more strongly transferred towards the heat pipe 3, in the thickness direction, a temperature further from the heat pipe 3 being higher than the temperature closer to the heat pipe 3. Such a temperature difference in the direction thickness is ΔΤ.
    According to FIG. 3, the first fuel 15 is arranged closer around the heat pipe 3. This means that the value 1 of the first fuel 15 is limited to a lower value in the core 32. For example, consider the two cases where
    The thickness of the first fuel 15 is 1 or Γ, in which Γ is greater than 1. When the first fuel 15 between 1 and Γ transfers the same amount of heat to the heat pipes 3, ΔΤ of the first fuel 15 is less than 1 is less than ΔΤ of the first fuel 15 less than Γ. Thus, the temperature difference inside the heart 32 is eliminated.
    As described above, the second fuel 16 produces less heat than the first fuel 15. Thus, the use of the second fuel 16 with a lower concentration of fissile material arranged around the first fuel 15 locally prevents a temperature increase even if the heat produced in the second fuel 16 is not easily transferred to the heat pipes 3. In addition, the second fuel 16 around the first fuel 15 maintains the value ΔΤ in the first fuel 15.
    In other words, the first fuel 15 around the heat pipes 3 and the second fuel 16 around the first fuel 15 prevent the temperature as far as possible from the heat pipes 3 in the core 32 from becoming higher than in other parts of the core 32 In addition, this results in the heart producing more energy with a smaller temperature difference in the heart 32.
    The thickness of the first fuel 15 is preferably within an appropriate range obtained by preliminary experiments. For example, when 1 is shorter than the length of the appropriate range, the distance from the middle of the second fuel 16 to the heat pipes 3 increases. Then the heat in the middle of the second fuel 16 is less likely to be transferred to the heat pipe 3 and the temperature in the middle of the second fuel 16 increases. As a result, the temperature difference inside the heart 32 can increase.
    The first fuel 15 is arranged in the form of a cylinder around the heat pipe 3 in the embodiment shown. Between the first fuel 15 and the heat pipe 3, a clearance or gap 23 is present. The clearance or gap 23 can be in the form of a cylinder around the heat pipe 3. That is to say that the internal diameter of the first cylindrical fuel 15 can be greater than the external diameter of the heat pipe 3.
    - 13 During the operation of the nuclear reactor 2, the volume of the first fuel 15 and of the second fuel 16 expand compared to their volume before the operation of the nuclear reactor 2. The clearance 23 prevents the heart 32 from bursting taking into account the expansion of the first fuel 15 and of the second fuel 16.
    Before the start of operation of the nuclear reactor 2, the heat pipe 3 is covered with a metal sheet 24. The metal sheet 24 is made of metal which melts at the operating temperature of the nuclear reactor 2. For example the metal sheet 24 is made in gallium, sodium, lithium, lead, bismuth and alloys. The metal sheet 24 may comprise a single metallic layer or multiple metallic layers.
    When the metal layer 24 melts at a certain temperature during the operation of the nuclear reactor 2, the molten metal layer 24 fills the gap or gap 23. The molten metal layer 24 improves the efficiency of thermal conduction from the first fuel 15 to the heat pipe 3. During the operation of the nuclear reactor 2, the metal layer 24 is liquid and flexible in the clearance or gap 23. The clearance or gap 23 and the metallic layer 24 prevent the core 32 from bursting due to the expansion of the fuels 15, 16.
    The metal layer 24 is not limited to being located between the first fuel 15 and the heat pipe 3. In certain embodiments, the metal layer 24 can be arranged between the first fuel 15 and the second fuel 16. The metal layer 24 can be arranged on other parts in the heart 32.
    The metal layer 24 is solid during manufacture and before the start of operation of the nuclear reactor 2. Thus, the metal layer 24 can easily cover the heat pipe 3. The load of the metal layer 24 can be adjusted by modifying the number of windings of the metal sheet around the heat pipe 3. After the start of operation of the nuclear reactor 2, the metal layer 24 becomes liquid in the gap or gap 23.
    The metal layer 24 is not limited to a metal sheet before the
    Start of operation of the nuclear reactor 2. Before the operation of the nuclear reactor 2, the metal layer 24 can be composed of metallic particles or of metallic powder filling the clearance or gap 23.
    A modified nuclear reactor 2 is described with reference to FIG. 4. It may be noted that the same configurations as those described above are given the same reference numbers, thus omitting a redundant description.
    Figure 4 is an enlarged cross section of the heart 32 perpendicular to the heat pipes 3. On the enlarged cross section of the heart 32, a first zone 25 and a second zone 26 are arranged. There are more heat pipes 3 per unit area in the first area 25 than in the second area 26. The second area 26 is arranged around the first area in cross section of the core 32, perpendicular to the heat pipes 3.
    The heat transmitted in the heat pipes 3 per unit area in the first area 25 is greater than that per unit area in the second area 26, due to the difference in the number of heat pipes 3 between the first area 25 and the second area 26 In the second zone 26, there may not be a heat pipe 3.
    All of the heat pipes 3 have the same shape and the same diameter. A distance between two adjacent heat pipes 3 in the first area 25 is less than that in the second area 26. Thus, the heat to be transferred by the heat pipes 3 per unit area in the second area 26 is less than that per unit area in the first zone 25. The transfer of the heat produced in the second zone 26 is thus weaker by the heat pipes 3 than in the first zone 25.
    As in FIG. 3, the first zone 25 comprises the first fuel 15 containing fissile material at a first concentration and the second fuel 16 containing fissile material at a second concentration. The second concentration is lower than the first concentration. The distance between the first fuel 15 and a heat pipe 3 is less than that between the second fuel 16 and the heat pipe 3. For example,
    The first fuel 15 is positioned around a lateral surface of the heat pipe 3 parallel to a central axis of the heat pipe 3 and the second fuel 16 is positioned on an external side of the first fuel 15. In FIG. 4, the second fuel 16 is arranged around the first fuel 15.
    The second zone 26 comprises the third fuel 17 containing fissile material at a third concentration and a fourth fuel 18 containing fissile material at a fourth concentration. The distance between the third fuel 17 and a heat pipe 3 is less than that between the fourth fuel 18 and the heat pipe 3. For example, the third fuel 17 is positioned around a lateral surface of the heat pipe 3 parallel to a central axis of the heat pipe and the fourth fuel 18 is positioned on an external side of the third fuel 17. In FIG. 4, the fourth fuel 18 is arranged around the third fuel 17.
    The concentration of fissile material in the first zone 25 is different from that in the second zone 26.
    The second concentration is lower than the first concentration. The third concentration is lower than the second concentration. The fourth concentration is lower than the third concentration. Thus, the concentration of fissile material per unit area in the second zone 26 is lower than that of the first zone 27 (or 25). Thus, an increase in the temperature in the second zone 26 is suppressed, even if the heat transferred into the heat pipes 3 per unit of surface in the second zone 26 is less than that per unit of surface in the first zone 25.
    The fissile material concentration of the first fuel 15 or of the second fuel 16 may be identical to the fissile material concentration of the third fuel 17 or of the second fuel 16. For example, the fissile material concentration of the second fuel 16 may be identical to that of the third fuel 17. The fissile material concentration of the first fuel 15 may be identical to that of the third fuel 17 when the fissile material concentration of the fourth fuel 18 is lower than that of the second fuel 16. The fissile material concentration of the second fuel
    -16combustible 16 can be identical to that of the fourth fuel 18 when the fissile material concentration of the third fuel 17 is lower than that of the first fuel 15.
    The first fuel 15 is of a cylindrical shape surrounding the heat pipe 3. The first fuel 15 envelops the heat pipe 3. The central axis of the first fuel 15 is parallel to that of the heat pipe 3. The second fuel 16 is a quadrangular prism surrounding the first fuel 15. The second fuel 16 is arranged around the first fuel 15. The central axis of the second fuel 16 is parallel to that of the first fuel 15. The third fuel 17 is of a cylindrical shape surrounding the heat pipe 3. The third fuel 17 envelops the heat pipe 3. The central axis of the third fuel 17 is parallel to that of the heat pipe 3. The fourth fuel 18 is a quadrangular prism surrounding the third fuel 17. The fourth fuel 18 is arranged around the third fuel 17. L the central axis of the fourth fuel 18 is parallel to that of the third fuel 17.
    The first cells 21 comprise a pair of the first fuel 15 and the second fuel 16. The second cells 22 comprise a pair of a third fuel 17 and a fourth fuel 18. On a cross section of the heart 32 perpendicular to its central axis , a section of the second cells 22 is greater than that of the first cells 21. For example, in FIG. 4, the vertical and horizontal dimensions of the second cells 22 are respectively equal to twice that of the first cells 21.
    The first four cells 21 are positioned around a control bar 19, each cell facing the control bar 19. The control bar 19 is in the same position as the central axis of the heart 32. In order to control the fission reaction, extraction and insertion of the control bar 19 are controlled. The first area 25 produced from the first four cells 21 is an area of greater importance. The control bar 19 arranged in the first zone 15 as a zone of higher importance improves the efficiency of neutron absorption by the
    - 17 control 19. This means that fewer control bars make it possible to control the power of nuclear reactor 2.
    The extraction and insertion of the control bar 19 can be controlled by control bar drive mechanisms. The control bar 19 is not limited to a bar. For example, the control bar 19 may be made of a material which expands with a rise in temperature. The control bar 19 oscillates in the core 32 by expansion and absorbs neutrons.
    An embodiment of a modified nuclear reactor 2 is described with reference to the following FIG. 5. It can be noted that the same configurations as those described above are assigned the same reference numbers, thus omitting a redundant description.
    Figure 5 is an enlarged cross-sectional view of the nuclear reactor
    2. This cross-sectional view is perpendicular to the direction parallel to the central axis of the heat pipe 3. The first fuel 15 contains fissile material at a first concentration. The second fuel 16 contains fissile material at a second concentration. The first fuel 15 is positioned around a lateral surface of the heat pipe 3 parallel to the central axis of the heat pipe
    3. The second fuel 16 is positioned farther from the heat pipe 3 than the first fuel 15.
    A layer 31 has a plurality of heat pipes 3 parallel to their central axes. The direction in which the heat pipes 3 are aligned in parallel is defined as the first direction. The layer 31 includes the first fuel 15 around the heat pipe 3. The layer 31 also includes the second fuel 16 around the first fuel 15 around each of the heat pipes 3 close to each other in the layer 31. A thickness of the second fuel 16 , perpendicular to the first direction and to the third direction, is identical to the external diameter of the first fuel 15 or slightly greater than the external diameter of the first fuel 15.
    The first heat conductor 27 is arranged along a lateral surface of the layer 31 and parallel to the third direction. Conductivity
    Thermal of the first heat conductor 27 is greater than that of the second fuel 16. The first layer 31 is between the first two heat conductors 27. The first layer 31 is, for example, based on beryllium.
    In the second fuel 16, most of the heat produced near the first fuel 15 is likely to be transferred to the heat pipe 3. In the second fuel 16, most of the heat produced further from the first fuel 15 is more difficult to transfer to the heat pipe 3. This means that the heat in the middle of the second fuel 16 is difficult to transfer. The central part of the second fuel 16 is thus designated a low conductivity zone 28.
    The first heat conductors 27 are arranged in order to transfer heat in the low conductivity zone 28 as close as possible to the first fuel 15. In other words, the heat produced in the second fuel 16 is transferred to the first fuel 15 at by means of the first heat conductors 27. In addition, the heat in the first fuel 15 is transferred to the heat pipe 3. Thus, an increase in the temperature in the second fuel 16 is suppressed. The first heat conductor 27 functions as a by-pass element by transferring heat from the second fuel 16 to the first fuel 15.
    The first heat conductor 27 made of beryllium has a high thermal conductivity and increases the neutrons radiated from the fuel 15, 16 in order to facilitate the fission reaction. The beryllium contained in the first heat conductor 27 increases the neutrons by a reaction (n, 2n) and improves the criticality of the fuel 15, 16. The material contained in the first heat conductor 27 is not limited to beryllium. For example, the material can be copper, a liquid, or another solid.
    An embodiment of a modified nuclear reactor 2 is described with reference to Figure 6 below. It can be noted that the same configurations as those described above are assigned the same reference numbers, thus omitting a redundant description.
    FIG. 6 is an enlarged cross-sectional view of the nuclear reactor 2. This cross-sectional view is perpendicular to the third direction. The first fuel 15 contains fissile material at a first concentration. The second fuel 16 contains fissile material at a second concentration. The first fuel 15 is positioned around a lateral surface of the heat pipes 3 parallel to a central axis of the heat pipes 3. The second fuel 16 is positioned further away from the heat pipes 3 than the first fuel 15.
    The first layer 41 and the second layer 42 comprise a plurality of heat pipes 3 respectively parallel to their central axes. Each layer 41, 42 comprises the first fuel 15 around a heat pipe 3. Each layer 41, 42 also includes the second fuel 16 around the first fuel 15 around each of the heat pipes 3 close to each other in layer 41, 42. The thickness of the second fuel 16, perpendicular to the first direction and to the third direction, is identical to the external diameter of the first fuel 15 or slightly greater than the external diameter of the first fuel 15. The second layer 42 is stacked on the first layer 41 in the direction perpendicular to the first direction and the third direction.
    The heat pipe 3 of the second layer 42 is disposed between two heat pipes 3 close to each other in the first layer 41. According to this order, as seen in the second direction, the overlap of the heat pipes 3 in the layers close to it. one of the other is prevented. Thus, an increase in local temperature of the heart 32 is suppressed.
    The layers 41, 42 are interposed respectively between the first two heat conductors 27. The first heat conductor 27 is in the form of a plate. The thermal conductivity of the first heat conductor 27 is higher than that of the second fuel 16. A moderator 43 is arranged between the first layer 41 and the second layer 42, the layers 41 and 42 are interposed between the first heat conductors 27. The moderator 43 is, for example, made on the basis of a solid metal hydride. For example, the moderator 43 comprises calcium hydride, zirconium hydride,
    -20 lanthanum hydride, praseodymium hydride or graphite.
    In FIG. 6, the first heat conductor 27 made of beryllium is arranged closer to the fuels 15, 16 than the moderator 43. Thus, the neutrons reach the first heat conductor 27 without passing through the moderator 43. The first conductor heat 27 increases the neutrons by a reaction (n, 2n) without any influence on the deceleration caused by the moderator 43.
    A second heat conductor 44 is arranged in the second fuel 16 in the layers 41, 42 and parallel to the first direction. The second heat conductor 44 is arranged between two heat pipes 3 in a layer. A third heat conductor 45 connects two overlapping layers which are in the first layer 41 and the second layer 42. One end of the third heat conductor 45 is closer to the heat pipe 3 than the other end. In other words, the third heat conductor 45 connects the second fuel 16 closest to the heat pipe 3 in the first layer 41 and the low conductivity zone 28 in the second layer 42. The other third heat conductor 45 connects the second fuel 16 closest to the heat pipe 3 in the second layer 42 and the low conductivity zone 28 in the first layer 41. The third heat conductor 45 is parallel to the second direction.
    The heat conductors 44, 45 are in the form of a plate or a bar. The thermal conductivity of the heat conductors 44, 45 is higher than that of the second fuel 16. The thermal conductivity of the heat conductors 44, 45 may be identical to or greater than that of the first heat conductor 27. The heat conductors 44, 45 are made of materials with a high thermal conductivity such as beryllium or copper. The heat conductors 44, 45 can be liquid or solid.
    The heat conductors 44, 45 transfer the heat produced in the low conductivity zone 28 as close as possible to the first fuel 15. The heat conductors 44, 45 transfer the heat produced as far as possible from the heat pipe 3 as close as possible to the first fuel 15 So an increase of
    -21 temperature caused by the heat produced in the low conductivity zone is suppressed.
    The heat 29 produced in the second fuel 16 is transferred to the first fuel 15 through the first heat conductor 27. The heat is transferred to the heat pipe 3 through the first fuel 15. Thus, a rise in temperature in the second fuel 16 is deleted.
    An embodiment of a modified nuclear reactor 2 is described with reference to Figures 7 to 16 below. It can be noted that the same configurations as those described above are assigned the same reference numbers, thus omitting a redundant description.
    The nuclear reactor 2 and the core 32 are each cylindrical. The heart 32 includes a plurality of heat pipes 3 parallel to the central axis of the heart 32. Each of the heat pipes 3 has an identical structure. Figure 7 is a cross-sectional view of a nuclear reactor, perpendicular to the third direction.
    As shown in FIG. 8, the layers 51, 52, 53, 54 are concentrically arranged cylinders which include the heat pipes 3 and the first fuels 15.
    The third layer 53 is inside the fourth layer 54. The second layer 52 is inside the third layer 53. The first layer 51 is inside the second layer 52. The layers 51, 52 , 53, 54 are each in a cylindrical shape. This arrangement of layers 51 to 54 improves the efficiency of heat transfer. This arrangement of layers 51 to 54 also contributes to the miniaturization of nuclear reactor 2.
    Figure 8 is a cross-sectional view of a nuclear reactor quarter 2, perpendicular to the third direction. The control bar 19 is arranged on the central axis of the heart 32. The layers 51, 52, 53, 54 are arranged in multiple layers of cylindrical shape concentrically around the control bar 19. The control bar 19 is arranged adjacent to the first layer 51.
    In each of the layers 51, 52, 53, 54, the same numbers of heat pipes 3 are arranged at regular intervals. So the number of heat pipes 3 per unit of
    -22surface decreases with the distance from the center of the core 32, so that the number of heat pipes 3 per unit area of the first layer 51 is highest in the core 32. The number of heat pipes 3 per unit area of the fourth layer 54 is the weakest in core 32.
    The first layer 51 is defined as a first zone. The second layer 52 is defined as a second zone. The third layer 53 is defined as a third zone. The fourth layer 54 is defined as a fourth zone. The heat transferred to the heat pipes 3 per unit of area in the first zone is greater than that of the second zone. The heat transferred to the heat pipes 3 per unit of area in the second zone is greater than that of the third zone. The heat transferred to the heat pipes 3 per unit of area in the third zone is greater than that of the fourth zone.
    The third zone tends to have the highest temperature. In the third zone, the heat transferred to the heat pipes 3 per unit area is less than that of other zones. Except sometimes, the heat transferred to the heat pipes 3 per unit area in the fourth zone is less than that of the third zone. However, the temperature in the fourth zone is lower than that in the third zone because there is no fuel outside the fourth layer 54.
    The moderators 43 are arranged between the first layer 51 and the second layer 52, between the second layer 52 and the third layer 53 and between the third 53 and the fourth layer 54. A neutron reflector 55 is on the fourth layer 54. The neutron reflector 55 contains beryllium. The neutron reflector 55 reflects neutrons from the fuel towards the center of the core 32.
    As shown in FIG. 9, showing a part around a heat pipe 3 in FIGS. 7 and 8, the first fuel 15 is placed around a lateral surface of the heat pipe 3 parallel to a central axis of the heat pipe 3. The second fuel 16 is arranged outside the first fuel 15, farther from the heat pipe 3 than the first fuel 15. The first fuel 15
    -23 contains fissile material at a first concentration. The second fuel 16 contains fissile material at a second concentration. The first concentration is higher than the second concentration.
    A first direction is a circumferential direction of each of the layers 51, 52, 53, 54. The second fuel 16 is arranged along the first direction between the respective first fuels 15 near each other in the layers 51 , 52, 53, 54. A respective first heat conductor 27 respectively comes into contact with the lateral surfaces of the layers 51, 52, 53, 54 parallel to a central axis of a respective heat pipe 3. Each first heat conductor 27 comes into contact with a first fuel 15 and a second fuel 16. The contact surface of the first fuel 15 and of the first heat conductor 27 is curved. The contact surface is thus greater than that when the contact surface is planar. The upper contact surface improves the thermal conduction between the first heat conductor 27 and the first fuel 15.
    The moderator 43 is arranged along the first heat conductor 27.
    The thickness of the first heat conductor 27 is smaller than that of the moderator 43. The neutrons coming from the fuels 15, 16 can pass through the first heat conductor 27. The first heat conductor 27 closer to the fuels 15, 16 tends to increase the number of neutrons due to reflection. Neutrons produced in one layer are slowed down by moderator 43 and a fission reaction is likely to occur until a neutron reaches another layer.
    The neutrons strike the first fuel 15 effectively in the core 32, in which the layers 51, 52, 53, 54 are arranged in the form of multiple concentric layers of cylindrical shape. As shown in Figure 8, neutrons 56 from the first layer 51 can strike the first fuel 15 in the second layer 52. In addition, neutrons 56 from the second layer 52 can strike the first fuel 15 in the third layer 53, or can strike the first fuel 15 in the fourth layer 54.
    The concentration of fissile material in the fuel in a layer is not limited to being identical. The concentration of fissile material may be different in the third direction. For example, the first and second fuels 15, 16 in each of the layers 51, 52, 53, 54 may have a plurality of sections 57 divided in the third direction. In each of sections 57, the concentration in fuels 15, 16 can be adjusted appropriately.
    FIGS. 10 and 11 show how the concentrations of fissile material in the first and second fuels 15, 16 can vary in different sections 57 depending on the direction of the height or third direction in each of the different layers 51, 52, 53, 54.
    The concentration of fissile material in the first fuel 15 of each of the sections 57 is described in Figure 10. The Z axis in Figure 10 is the third direction or direction of the height. The R axis in Figure 10 is the second direction. The first fuel 15 is positioned in each section 57.
    According to Figure 10, each fissile material concentration of the first fuel 15 in sections 57 is 20% or 8%. In layers 51, 52 and 54, the fissile material concentration of the first fuel 15 in each section 57 is 20%. In the third layer 53, the fissile material concentration of the first fuel 15 is 20% or 8%. In the third layer 53, the heat transferred to the heat pipe 3 per unit area is different in the third direction. The heat transferred to the heat pipe 3 per unit area in the middle of the heart 32 may be less than that in the other parts. The heat transferred to the heat pipe 3 per unit area in the third layer 53 may be less than that in the other parts.
    The concentration of fissile material in the first fuel 15 from the center of the core 32 in the third direction, the shaded parts in FIG. 10, may be lower than in the other parts. Due to this position of the material, the difference on the temperature in the core 32 can better be eliminated.
    The concentration of the first fuel 15 in the first layer 51, the
    Second layer 52, the third layer 53 and the fourth layer 54 are Lll, L12, L13 and L14 respectively. The average concentration of the first fuel 15 can then be L11 = L12 = L14> L13, or L11> L12> L14> L13, or Lll> L12> L14> L13, or Lll> L12> L13> L14.
    The concentration of fissile material in the second fuel 16 of each of the sections 57 is described in FIG. IL The axis Z of FIG. 10 is the third direction or direction of the height. The R axis in Figure 10 is the second direction. The second fuel 16 is positioned in each section 57.
    As shown in Figure 11, each fissile material concentration in the second fuel 16 on sections 57 is 20%, 15%, 8%, 5% or 3%. The heat transferred to the heat pipe 3 in the heart 32 differs in the second direction and the third direction. For example, the heat transferred to the heat pipe 3 in the middle of the third direction in the heart 32 is less than that of the other parts. In particular, the heat transferred to the heat pipe 3 in the third layer 53 is less than that of the other parts.
    The concentration of fissile material in the second fuel 16 from the center of the core 32 in the third direction, the shaded parts in FIG. 11, may be lower than those of the other parts. Due to this position of the material, the difference in temperature in the core 32 can better be eliminated.
    The concentration of fissile material in the second fuel 16 on the first layer 51, the second layer 52, the third layer 53 and the fourth layer 54 is L21, L22, L23 and L24, respectively. The average concentration of the first fuel 15 can then be L21> L22 = L24> L13, or L21> L22> L24> L23, or L21> L22> L24> L23, or L21> L22> L23> L24.
    The average fissile material concentration of the first fuel 15 and the second fuel 16 in the layers 51, 52, 53 and 54 are described respectively as the first average concentration, the second average concentration, the third average concentration and the fourth
    -26 average concentration. The average concentration in each layer is not limited to being identical to that of the other layers. For example, the second average concentration may be less than the first average concentration, the fourth average concentration may be less than the second average concentration, and the third average concentration may be less than the fourth average concentration.
    The concentration of fissile material in fuels 15 and 16 is defined in the third direction and the second direction. Due to this position of the fuel, the temperature difference in the core 32 can better be eliminated.
    The heat produced per unit of time in each section 57 is described with reference to Figures 12 and 13. The unit of each numerical value is W / cm3. Figure 12 shows the heat produced in the first fuel 15 in each section 57. Figure 12 corresponds to Figure 10. Figure 13 shows the heat produced in the second fuel 16 in each section 57. Figure 13 corresponds to the figure 11.
    FIG. 14 indicates the heat produced in the first fuel 15 in each section 57 when the concentration of fissile material in the first fuel 15 in each section 57 is identical to that of the other sections 57. As shown in FIG. 14, the concentration of fissile material in the first fuel 15 in each section 57 is 20%. FIG. 15 indicates the heat produced in the first fuel 16 in each section 57 when the concentration of fissile material in the first fuel 16 in each section 57 is identical to that of the other sections 57. As shown in FIG. 15, the concentration of fissile material in the first fuel 16 in each section 57 is 15%.
    As shown in Figures 14 and 15, the heat in the middle in the third direction in each layer 51 to 54, the shaded parts in Figures 14 and 15, is higher than in the other parts. In particular, the heat produced at the center of the heart 32 in the third direction and the second direction is highest in the heart 32. The heat distribution of the heart 32
    -27 is a cosine distribution centered on the center of the heart 32. Thus, the temperature in the center of the heart 32 is much higher than in the other parts.
    As shown in Figure 12, the section 57 producing the most heat in the second layer 52 does not overlap the section 57 producing the most heat in the third layer 53 in the second direction. The section 57 producing the most heat in the third layer 53 does not overlap the section 57 producing the most heat in the fourth layer 54 in the second direction. These arrangements prevent the increase in local temperature differences in the heart 32.
    As shown in Figure 13, the section 57 producing the most heat in the first layer 51 does not overlap the section 57 producing the most heat in the second layer 52 in the second direction. The section 57 producing the most heat in the second layer 52 does not overlap the section 57 producing the most heat in the third layer 53 in the second direction. The section 57 producing the most heat in the third layer 53 does not overlap the section 57 producing the most heat in the fourth layer 54 in the second direction. These arrangements prevent the increase in local temperature differences in the heart 32.
    A method of transferring heat from the inside of the heart 32 to the outside of the heart 32 is described below. Figure 16 is a process algorithm. On the algorithm, for example, step 11 is designated by SI 1.
    First, the first fuel 15 produces heat in S11. The heat produced in the first fuel 15 is transferred to the heat pipes 3 directly at S12 as the first transfer operation.
    The second fuel 16 produces heat in S13. The heat produced in the second fuel 16 is transferred to the first fuel 15 at S14. The heat produced in the second fuel 16 is transferred to the heat pipe 3 through the first fuel 15 in SI5 as a second transfer operation.
    The heat transferred to heat pipe 3 is transferred to the production section
    -28 of energy 5 in S16 as a transfer operation. The energy production section 5 produces electrical energy from heat from the heat pipe 3 in S17. The excess heat after SI7 is transferred to the radiator 6 so as to be eliminated in the atmosphere in S18.
    Although certain embodiments have been described, these embodiments are presented by way of example and are not intended to limit the scope of the embodiments. These new embodiments can be implemented in other different forms and different replacements, omissions and variants can be made on the latter without however departing from their spirit. These embodiments and their variants may be contained in the scope and spirit of the invention as well as in the scope of the invention and its equivalents mentioned in the description. For example, the metal sheet 24 can cover the heat pipes 3. The second heat conductor 44 and the third heat conductor 45 can be arranged in any one of the cores 32 described in the present application.
    The heat pipe 3 is not limited to containing liquid inside. A heat pipe 3 which does not have an internal cavity can be used. Heat pumps can be used rather than heat pipes 3.
    The first direction, the second direction, and the third direction can be the X axis, the Y axis, and the Z axis respectively. The first direction, the second direction, and the third direction can be the circumferential direction, the direction, respectively. radial and axial direction of the cylinder. The section perpendicular to the central axis of the heart 32 is not limited to a circle. The section perpendicular to the central axis of the heart 32 can be elliptical or oval.
    Obviously, numerous modifications and variations of the embodiments are possible in the light of the preceding teachings. It should therefore be understood that within the scope of the invention, the embodiments can be implemented in another way than specifically described here.
    权利要求:
    Claims (15)
    [1]
    1. Nuclear device (2), comprising: a heat pipe (3);
    a first fuel (15) positioned around a lateral surface of the heat pipe parallel to a central axis of the heat pipe, the first fuel containing a fissile material at a first concentration;
    a second fuel (16) positioned on an outer side of the first fuel and containing fissile material at a second concentration lower than the first concentration; and a core (32) comprising a plurality of heat pipes arranged parallel to each central axis in the first fuel or in the first fuel and the second fuel.
    [2]
    2. The nuclear device according to claim 1, in which a concentration of the fissile material in a first zone is greater than that in a second zone and the heat transferred to the heat pipes from the second zone is less than the heat transferred to the heat pipes at from the first zone.
    [3]
    3. Nuclear reactor according to claim 2, in which the first zone contains more heat pipes than the second zone per unit area on a cross section of the core perpendicular to the central axis of the heat pipe.
    [4]
    4. The nuclear reactor according to claim 1, further comprising: a first layer which has the plurality of heat pipes parallel to their central axes, the second fuel being around the first fuel around each of the heat pipes near one of the other;
    a first heat conductor along a lateral surface of the first layer and parallel to the central axis, the thermal conductivity of the first heat conductor being greater than that of the second fuel.
    [5]
    5. Nuclear reactor according to claim 3, wherein the first heat conductor contains beryllium.
    -306. The nuclear reactor of claim 1, further comprising: a layer which includes the plurality of heat pipes parallel to the central axes, the second fuel being around the first fuel around each of the heat pipes close to each other; and a second heat conductor positioned in the second fuel.
    [6]
    7. A nuclear reactor according to claim 1, further comprising: a layer which includes the plurality of heat pipes in parallel with the central axes, the second fuel being around the first fuel around each of the heat pipes close to each other ; and a heat conductor connecting two overlapping layers, wherein a first end of the heat conductor is closer to the heat pipe than a second end.
    [7]
    8. A nuclear reactor according to claim 1, further comprising: a first layer which comprises the plurality of heat pipes in parallel with the central axes, the second fuel being around the first fuel around each of the heat pipes near one of the other;
    a second layer which comprises the plurality of heat pipes in parallel with the central axes, the second fuel being around the first fuel around each of the heat pipes close to each other and covering the first layer;
    wherein a heat pipe of the second layer is positioned between two heat pipes close to each other in the first layer.
    [8]
    9. Nuclear reactor according to claim 1, further comprising a metal layer between the heat pipe and the first fuel, comprising a metal, in which a temperature of the melting point of the metal is higher than a temperature before a starting operation of the nuclear reactor and is not higher than an operating temperature of the nuclear reactor.
    [9]
    10. Nuclear reactor according to claim 1, in which the core comprises a plurality of cylinders arranged concentrically,
    -31 in which each of the cylinders is produced in a layer comprising the plurality of heat pipes in parallel with the central axes, the first fuel and the second fuel around the first fuel around each of the heat pipes close to each other.
    [10]
    11. The nuclear reactor according to claim 10, wherein the content of fissile material in the core differs along the axis of the heat pipe.
    [11]
    12. Nuclear reactor according to claim 10, in which the core is divided into multiple sections in the direction of the central axis of the core, in which a concentration of the fissile material in each section is adjusted according to a position of the section.
    [12]
    13. A nuclear reactor according to claim 10, wherein a point producing maximum heat in one layer does not overlap a point producing maximum heat in a next adjacent layer.
    [13]
    14. Nuclear reactor according to claim 10, wherein the content of the fissile material in the core differs in a radial direction over a cross section of the core perpendicular to the central axis of the heat pipe.
    [14]
    15. The nuclear reactor according to claim 14, further comprising a control rod arranged on a central axis of the heart, in which the content of the fissile material in the central part of the heart, near a lateral surface of the heart. parallel to a central axis of the heart, and that near a midpoint of a length of the heart parallel to the central axis, are less than those of other parts in the heart.
    [15]
    16. A method of heat transfer from the interior of a nuclear reactor core to the exterior of the core, comprising:
    transferring heat produced in a first fuel to a heat pipe positioned in the first fuel, the first fuel containing fissile material at a first concentration;
    transferring heat produced in a second fuel positioned on an external side of the first fuel into the heat pipe by the first fuel, the second fuel containing the fissile material at a second concentration lower than the first concentration; and
    The transfer of the heat produced in the first fuel and the second fuel outside the core.
    1/13
    Ί
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    同族专利:
    公开号 | 公开日
    JP2018021763A|2018-02-08|
    US10692612B2|2020-06-23|
    US20180033501A1|2018-02-01|
    JP6633471B2|2020-01-22|
    FR3054715B1|2020-02-28|
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    法律状态:
    2018-07-09| PLFP| Fee payment|Year of fee payment: 2 |
    2019-07-12| PLFP| Fee payment|Year of fee payment: 3 |
    2020-06-25| PLFP| Fee payment|Year of fee payment: 4 |
    2021-06-11| PLFP| Fee payment|Year of fee payment: 5 |
    优先权:
    申请号 | 申请日 | 专利标题
    JP2016151201|2016-08-01|
    JP2016151201A|JP6633471B2|2016-08-01|2016-08-01|REACTOR AND HEAT REMOVAL METHOD FOR REACTOR|
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