• 专利附录
  • 专利说明
  • 权利要求
  • 类似技术
  • 同族专利
  • 引用文献
  • 法律状态
  • 优先权
    • 专利摘要:
    USED NUCLEAR FUEL POOL An auxiliary system for cooling a pool of spent nuclear fuel through a submersible heat exchanger to be located inside the pool. In each assembly or installation, a single circuit or series of cooling fluid circuits (for example, sea water or drinking water) is circulated. The system is modular, ready and easily installed during an emergency, and can be self-operating with its own power source. Multiple sets can be used in parallel in order to perform the required degree of cooling of the used fuel pool required.
    公开号:BR112013024759B1
    申请号:R112013024759-2
    申请日:2012-01-24
    公开日:2021-01-26
    发明作者:Timothy M. Lloyd；David Rasmussen；Joel Kulesza
    申请人:Westinghouse Electric Company Llc；
    IPC主号:
    专利说明:

    [0001] [0001] This order claims priority to provisional Order Serial No. 61 / 469,184, filed on March 30, 2011, entitled SELFOPERATING EMERGENCY SPENT FUEL POOL COOLING SYSTEM. BACKGROUND OF THE INVENTION 1. Field of the Invention
    [0002] [0002] This invention relates generally to cooling systems used to cool water in a nuclear reactor power generation facility and, more particularly, to a temporary cooling system designed to supplement existing cooling systems for the Used Fuel Pool and accommodate emergency conditions experienced in such a facility. 2. Related Technique
    [0003] [0003] In nuclear power generation facilities, a reactor vessel housing nuclear fuel and water is positioned, which is generally referred to as a refueling cavity or a reactor cavity. During power generation, a primary fluid refrigerant, usually water, is heated by nuclear fuel, and heat is used to generate steam to generate electrical power. During refueling interruptions and other periods, when the reactor is not operating, the fuel's decay heat continues to heat the water inside the reactor vessel. The water must be cooled to a desired level, before the fuel can be removed from the vessel and transferred to a pool of spent fuel from the facility through the reactor cavity. The residual decay heat generated by the reactor core is cooled during shutdown by a permanently installed residual heat removal system. The residual heat removal system provides cooling by heat exchange, for the heat of decay coming from the fuel inside the reactor core during shutdown. The heat removal capacity of this system is necessarily great. During normal shutdown, the residual heat removal system is operated for a number of days in order to remove the heat from the fuel's decay to a point where the fuel can be removed from the core. This is due to the fact that the spent fuel pool, the eventual storage location for the fuel, has a permanently installed cooling system, which does not have sufficient cooling capacity to remove the high level of residual heat generated by the fuel immediately following the shutdown of the plant.
    [0004] [0004] Thus, in situations requiring removal of fuel from the reactor core, the configuration of the permanent cooling system of current nuclear plants requires that the residual heat removal system be operated for a period of days in order to cool the fuel at a point where it can be safely removed to the spent fuel pool to allow maintenance of the reactor, such as refueling or decontamination of components, such as the reactor recirculation system. U.S. patent 5,268,942 describes an auxiliary cooling system that can be permanently stored within the containment to increase the residual heat removal system and accelerate this process. Without such an auxiliary system, maintenance equipment has to wait several days until the residual heat removal system adequately cools the reactor core, before proceeding to remove fuel. This cooling downtime increases the total plant shutdown period, thereby increasing the cost of a shutdown operation, resulting in lost revenue, as well as the cost of replacement power acquired during shutdown. On the other hand, the cost of such a system or the cost of increasing the capacity of the used fuel pool cooling system is expensive.
    [0005] [0005] On March 11, 2011, the earthquake and tsunami in Japan led to a serious breakdown and blackout of the Fukushima Daiichi Nuclear Power Plant. Although the plant successfully shut down after the earthquake, the next tsunami rendered the plant unable to restore power to the cooling systems responsible for cooling the reactor and the pool of spent fuel. This resulted in fusion of core fuel in three units, loss of water inventory, potential fuel failures in the spent fuel pools, and radioactive release into the environment. The increased scrutiny is being focused on the world's nuclear power plants, and the need to be able to respond to events that are beyond the basis of the nuclear plant's original design. The embodiments described here expand under the capacity of existing systems in a way that allows an auxiliary cooling system to be quickly deployed and installed to provide a self-contained, self-contained means of removing heat from decay from the used fuel pool to the equipment normal plant can be returned for maintenance.
    [0006] [0006] Thus, it is an objective, of the embodiments described here, to provide an auxiliary installed cooling system or a portable cooling system that can be readily transported to a nuclear power plant site and quickly installed and activated to provide adequate cooling for the used fuel pool, the event of the native cooling system is inoperable or proves inadequate for any reason.
    [0007] [0007] It is another objective to provide such a cooling system that is self-contained, and it is a self-sufficient means of removing heat from decay from the spent fuel pool until normal plant equipment can be returned for maintenance. SUMMARY
    [0008] [0008] These and other objectives are achieved by the embodiments described here, which provide a self-propelled waste heat removal system that can be transported to and quickly connected to a pool of spent nuclear fuel at least partially charged with a liquid, such as like water or borated water. The residual heat removal system includes a cooling duct disposed within the spent fuel pool within the liquid in which the spent fuel is submerged, with the inside of the cooling duct insulated from the liquid within the used nuclear fuel pool. A coolant reservoir, away from the spent fuel pool, is connected to the cooling duct by a coupling line through which a coolant can be circulated from the coolant reservoir through the cooling duct and out of a receiving tank. . A circulation mechanism is provided to circulate the refrigerant through the coupling line. In one embodiment, the circulation mechanism is a pump powered by a primary or auxiliary power source. Preferably, the pump is a pump powered by diesel or gasoline. In one embodiment, the diesel or gas powered pump is a fire brigade truck. Alternatively, the auxiliary power source is a generator engine or battery. In one embodiment, in which the cooling system is permanently installed, the circulation mechanism includes a control unit that activates the circulation mechanism when the liquid in the spent fuel pool rises above a pre-selected temperature .
    [0009] [0009] In yet another embodiment, the cooling duct is a cooling coil, and preferably the cooling duct comprises a plurality of cooling ducts, for example, cooling coils that are connected in parallel to the coupling line. , possibly using multiple power sources and / or coolant reservoirs. Where practically available, the coolant can be sea water or, alternatively, water from any other nearby source. In addition, a cooling tower can be associated with the receiving tank to cool the refrigerant before it is discharged into the receiving tank. Desirably, the cooling duct is constructed of a material resistant to sea water, such as a copper-nickel alloy selected from the group 90/10, 70/30 or Monel. BRIEF DESCRIPTION OF THE DRAWINGS
    [0010] [00010] A further understanding of the invention can be gained from the following description of the preferred embodiments, when read in combination with the accompanying drawings in which: Figure 1 is a schematic representation of the layout of the relevant components of a typical light water nuclear reactor power generation installation, having an embodiment of an auxiliary residual heat removal system that can employ the benefits of the embodiments described here; Figure 2 is a schematic view of the used fuel pool, illustrated in Figure 1, which incorporates the auxiliary used fuel pool cooling system described here; and Figure 3 is a perspective view of a submersible cooling coil, which can be used in the embodiment shown in Figure 2. DESCRIPTION OF THE PREFERRED EMBODIMENT
    [0011] [00011] As shown in Figure 1, in a typical light water reactor nuclear power generation facility, only the pertinent parts are shown, a reactor construction 23 contains a reactor vessel 2, which contains a core 3 comprising numerous nuclear fuel elements 4, usually in the form of fuel bundles, generally referred to as fuel assemblies. During power generation operations, the reactor vessel 2 is closed from the top or head 5. The reactor vessel 2 is positioned inside a reactor cavity 6 which, in some designs, is fluidly connected to a pool of spent fuel 7 during stops. However, even in projects where the reactor cavity is connected to the spent fuel pool during shutdowns, containment insulation during operation requires that the water from the spent fuel pool be separated from the water in the refueling cavity and reactor cavity. In the embodiment of the installation shown in Figure 1, the spent fuel pool 7 is separated from the reactor cavity by a wall 8 having a lockable opening 9, closed by a gate (not shown) or other means known in the art to isolate the spent fuel pool 7 from reactor cavity 6. Since various embodiments of nuclear power generation facilities are possible, used fuel pool 7 and reactor cavity 6 will be together and separately referred to as the “fuel pool” compound fuel ”10, which will refer to any point within the spent fuel pool 7 or reactor cavity 6. An example of an alternative embodiment of the compound fuel pool 10 is one in which the used fuel pool and the reactor cavities are separated by a duct (for example, a “fuel transfer channel”, not shown) instead of a wall 8. The spent fuel pool 7 typically contains a shelf fuel strips 11, which support bundles of spent fuel that are stored in the spent fuel pool 7.
    [0012] [00012] During power generation operations, the reactor head 5 is closed and the primary fluid 12, normally referred to as the reactor refrigerant (typically water), is contained within the reactor vessel 2 at an operational level 13 above the core 3. Core 3 heats the primary fluid 12 which is used to generate steam, which is used as the motivating force to create electricity. The extensive piping and additional equipment, used to generate force, are not relevant to instantaneous embodiments and thus are not shown. A reactor recirculation system 14 recirculates water within the reactor vessel 2 and is fluidly connected to a residual heat removal system 15 during shutdown. In the installation shown in Figure 1, the reactor recirculation system 14 includes an “A” circuit 16 and a “B” circuit 17. The recirculation is maintained by the circulation pumps 18. Valves 19 provide isolation from the reactor recirculation system 14 of the residual heat removal system 15 during power generation operations. Of course, many different piping and valve configurations are possible and vary from installation to installation.
    [0013] [00013] Installation 1 can be stopped for several reasons, including replacement of total or partial fuel, decontamination of components or for other reasons. Detailed shutdown procedures are required in order to maintain the security of the system. In order to remove the fuel bundles 4 from the core 3, the reactor head 5 is removed and the primary fluid level 12 is raised to a refill level 20 within the composite fuel pool 10. Following this step, the lockable opening 9 is activated to an open position, allowing the primary fluid 12 to equal the refill level 20 both within the spent fuel pool 7 and the reactor cavity 6. Once the primary refill fluid level 20 is stable , the fuel bundles 4 can be lifted from the core 3 and placed on fuel racks 11. However, the initial heat of decay from the fuel bundles 4 must first be removed during this procedure, before the fuel bundles can be removed from the core .
    [0014] [00014] Once the core 3 is paralyzed, the heat of decay continues to be generated by the fuel 4. The residual heat removal system 15 is a heat exchange system designed to cool the primary fluid 12, removing the heat of initial decay generated in the system shutdown. As shown by the flow arrows 21, the residual heat removal system 15 cools the primary fluid 12 and recirculates the cooled primary fluid 12 back to the reactor vessel 2. As mentioned above, before the auxiliary waste heat removal system , described in US Patent 5,268,942, the traditional method of cooling the primary fluid 12 required operation of the residual heat removal system 15 for numerous days, until the initial large amount of decay heat was removed from the primary fluid 12. The amount of heat removed during the operation of the residual heat removal system can be in the order of 15,000,000 BTU / h. The residual heat removal system 15 was traditionally operated until the fuel bundles 4 were cooled to a point where they could be removed from the spent fuel pool 7, where the lower capacity used fuel pool cooling system 22 would continue to circulate primary fluid from the spent fuel pool 7 (as indicated by arrows 26), and remove the heat of decay at a much lower rate, for example, 1,000,000 BTU / h. The residual heat removal system 15 and the used fuel pool cooling system 22 are permanently installed in installation 1. Due to the permanent nature of the installation, as well as security, redundancy, licensing and contamination problems, the modification of the heating systems. permanent cooling would be impractical and very expensive.
    [0015] [00015] A temporary auxiliary cooling system 30 is described in US Patent 5,268,942 and provides immediate increased cooling capacity without additional permanent connections to installation 1. The cooling system 30 comprises a primary heat exchange system 31, which includes a primary heat exchanger to transfer heat from the primary fluid 12 to a secondary cooling fluid, a primary fluid pump, to circulate the primary fluid through the primary fluid heat exchanger, a primary fluid pump suction line 34 and a primary fluid discharge line 36. The primary fluid 12 is circulated in the primary heat exchange system 31, where heat is transferred to a secondary cooling fluid from a secondary heat exchange system. All heat exchange equipment, pumps and other components are said to be attached to drag platforms and temporarily located within facility 1. Due to severe space limitations within facility 1, the components of this auxiliary residual heat removal system 30 can be located within various locations within the facility 1. Due to the radioactive particles circulating in the primary heat exchange system 31, it is preferable to locate the primary heat exchange system 31 within the containment construction 23.
    [0016] [00016] In contrast to the previous system, the embodiments described here provide a much simpler and less expensive solution to supply auxiliary cooling for the used fuel pool at a significantly reduced cost. The embodiments described below can be built as an integral part of the installation or arranged when necessary in the event of an emergency. The system can be used with most any installation and, unlike previous systems, it can be portable and shared across multiple installations.
    [0017] [00017] In the event of an accidental loss of electricity, a loss of function in existing used fuel pool cooling systems, or both the ability to maintain adequate cooling and to cover the fuel used in a used fuel pool, is challenged. Typically, a pool of spent fuel will continue to maintain a degree of cooling by boiling the fluid inside the pool, typically boron water, for a period of days or weeks after the cooling capacity has been impaired. At the point where it becomes necessary to have an emergency or auxiliary used fuel cooling system, conditions can make it difficult or impossible to access the site to diagnose defects and restart existing backup systems. In extreme cases, it is conceivable that the used fuel pool environment cannot be accessible following the placement of an emergency backup cooling system. For this reason, it is desirable to specify a used fuel pool cooling system with extended unattended operation capabilities. It is also desirable that such a system be able to execute a program during a continuous and retracted loss of strength.
    [0018] [00018] The embodiments provided below provide cooling for a pool of spent fuel through the use of a submersible heat exchanger, which is submerged directly into the pool of spent fuel. Within each assembly or installation, a single circuit or series of cooling fluid circuits (for example, sea water, or drinking water) is circulated. The system described here is modular and autonomous, with the possible exceptions of AC power supplied or auxiliary cooling placed in the drinking water supply. Multiple sets or installations of the system can be used in order to achieve the desired degree of cooling of the spent fuel pool.
    [0019] [00019] The intended use of the system is to mitigate the effects of a loss of electricity, a failure of an existing used fuel cooling system, or both. The system provided here works by preventing or minimizing the boiling of mass in a pool of spent fuel and thus reduces the loss of fluid by the pool of spent fuel. In this way, additional cooling and fluid composition needs are prevented or at least mitigated.
    [0020] [00020] As mentioned earlier, conventional used fuel pool cooling systems circulate fluid through the used fuel pool through one or more heat exchangers located outside the used fuel pool; and, also, typically through filters, demineralizers, or other water processing components.
    [0021] • As chances de um vazamento da piscina de combustível usado para o equipamento associado com o sistema provido anexo ou dentro do ambiente são grandemente reduzidas. • A complexidade do sistema é substancialmente reduzida, deixando melhorias na confiabilidade do sistema e sustentando seu uso alternativo como um sistema autônomo que pode funcionar na ausência de um suprimento elétrico. • Em razão de somente os fluidos limpos (isto é, substancialmente não radioativos) circularem através das bombas e linhas do sistema, há risco extremamente pequeno de radiação exposta àquela operação ou manutenção do sistema, e nenhuma parte do sistema contribui para níveis de radiação na área circundante. O sistema não tem impacto negativo no ambiente de trabalho circundante. • A capacidade e intenção de imergir o trocador de calor em uma piscina de combustível usado carregada de fluido oferece proteção radiológica, tornando o sistema e componentes não radiologicamente piores do que o corpo de fluido existente dentro da piscina de combustível usado. • O peso, volume e grau de complexidade inferiores do sistema facilitam sua rápida montagem, teste e disposição, mesmo em locais de acesso remotos ou difíceis. • Um alto grau de resistência à radiação ou degradação química, devido às condições dentro da piscina de combustível usado e, possivelmente, do fluido de esfriamento. [00021] The system provided here offers numerous advantages through conventional systems of this type. The advantages include: • The chances of a leak from the fuel pool used for the equipment associated with the system provided attached or within the environment are greatly reduced. • The complexity of the system is substantially reduced, leaving improvements in the reliability of the system and supporting its alternative use as a stand-alone system that can function in the absence of an electrical supply. • Because only clean fluids (ie, substantially non-radioactive) circulate through the pumps and lines of the system, there is an extremely small risk of radiation exposed to that operation or maintenance of the system, and no part of the system contributes to radiation levels in the system. surrounding area. The system has no negative impact on the surrounding work environment. • The ability and intent to immerse the heat exchanger in a pool of spent fuel filled with fluid offers radiological protection, making the system and components non-radiologically worse than the body of fluid in the pool of used fuel. • The system's lower weight, volume and complexity facilitates rapid assembly, testing and arrangement, even in remote or difficult access locations. • A high degree of resistance to radiation or chemical degradation, due to conditions within the pool of spent fuel and possibly the cooling fluid.
    [0022] [00022] Such a system, as provided here, must be able to withstand the thermal and radiological environment of a pool of spent fuel. The system must be able to remove at least part of the heat of decay from a fully or partially loaded repository of spent nuclear fuel. The system must also provide a reasonable level of security that the cooling circuit, circulating through the immersed heat exchanger and the liquid body within the pool of spent fuel, will remain physically and chemically separated. In addition, the submerged part of the system will provide a reasonable degree of resistance to the anticipated radiation exposures to which it will be exposed. Finally, the material must be resistant to corrosion from the anticipated fluid types; these currently include sea water as the circulating coolant and a boric acid solution within the pool of spent fuel. The selection of a heat exchanger material must fulfill or address all of these interests. A suitable example of a well of such a material is a copper-nickel alloy (eg 90/10, 70/30 or Monel) or other material capable of withstanding the above mentioned environment.
    [0023] [00023] Figure 2 is a schematic of an embodiment of the concepts presented here and shows a used fuel pool 7 included within a containment construction 23. The used fuel pool has fuel assembly shelves 11 supported under the bottom of the pool, with a cooling duct 38 submerged above the shelves of the fuel assembly 11. The cooling duct 38 can be a heat exchanger, just like the serpentine tube 40 shown in Fig. 3. Referring again to Figure 2 , the heat exchanger 38 is connected by a coupling line 42, 44, having an inlet part 42 and an outlet part 44. The inlet part 42 has an inlet 46, preferably with a tensioner 48 which is submerged within of a body of water 50, which may be sea water (where appropriate), river water, a holding tank or other source of cooling fluid, generally referred to below as a coolant reservoir. The refrigerant 50 is circulated by a pump 52 driven by an auxiliary power source 54. Where the pump is electrically driven, it can be powered by the current line with a diesel generator support. Alternatively, the pump can be driven by diesel or gasoline and is preferably self-powered. The cooling fluid is driven through the inlet part of the coupling line 42, through the heat exchanger 38, and outwards through the outlet part 44 of the coupling line where it is preferably discharged back to the source 50 Where source 50 is a holding tank, the outlet portion of coupling line 44 may also include a cooling tower 56 or some other means of cooling the discharge before being recirculated through inlet 46, or where the discharge, at its high temperature, it would cause damage to the environment.
    [0024] [00024] In one embodiment, where the auxiliary cooling system 62 is included as a permanent installation, the pump 52 can be provided with a control system 58 that receives inputs from sensors 60, such as thermocouples or level sensors, inside the used fuel pool 7 which provides an indication of the condition of the pool. The control system can then automatically start pump 52, for example, if the spent fuel pool 7 rises above a predetermined temperature. Where the auxiliary cooling system 62 is disposed under somewhat emergency conditions, the coupling line 42, 44 can be a half-inch or larger fire hose and the auxiliary power source 54 operating the pump 52 can be a truck of the Fire Department.
    [0025] [00025] Thus, the used fuel pool fluid freely contacts the outer walls of the heat exchanger tube 38, and natural circulation and boiling in the used fuel pool helps in the exchange of heat through the outer wall within the mass fluid. Since the primary purpose of the system is to prevent boiling or to reduce the boiling rate, thermal conditions allowing less circulation in the pool of spent fuel at temperatures well below boiling will not entirely prevent the system from performing its function. In the event that a single set of the system removes less heat than is desired for equilibrium (ie, thermal output equal to total thermal losses), the temperature in the spent fuel pool will continue to increase or the boiling level will increase until vigorous conditions of heat removal appear on the outer surface of the heat exchanger tube. In addition, before this point, the circulation of fluid in the spent fuel pool, due to temperature gradients, will provide substantial mixing, tending to achieve a greater thermal gradient on and near the external surface of the heat exchanger. These conditions, coupled with the selection of a highly efficient thermal conductor, such as copper or copper-nickel alloy (90/10, 70/30, Mondel, etc.), will produce high thermal efficiencies for the system. The discharge of clean external cooling fluid preferably occurs outside the building containing the spent fuel pool, but it can be captured or retained in an alternative medium that could include, for example, the use of a holding tank in which samples can be used. taken to estimate the possibility of any leakage or degradation of material.
    [0026] [00026] Although specific embodiments of the invention have been described in detail, it will be noted by those skilled in the art that various modifications and alternatives to these details could be developed in the light of the overall teachings of the description. For example, two or more sets of cooling ducts can be connected in parallel with a single or multiple coupling lines to increase the cooling capacity of the system. The parallel cooling duct system can share a circulation mechanism or two or more of the cooling ducts could have an independent circulation mechanism. In addition, the coupling lines can be connected to different refrigerant sources respectively to ensure more redundancy, adequate amounts of refrigerant, and to reduce the impact on the environment. Therefore, the particular embodiments described are intended to be illustrative only and not to limit the scope of the invention, which is to be provided in the full range of the appended claims and any and all equivalents thereof.
    权利要求:
    Claims (15)
    [0001]
    Pool of spent nuclear fuel (7) at least partially charged with a liquid comprising water, characterized by the fact that it includes: a cooling duct (38) directly immersed inside the liquid inside the spent fuel pool (7), in direct heat exchange relationship with the liquid and having the inside of the cooling duct isolated from the liquid inside the used nuclear fuel pool ; a coolant reservoir (50), away from the spent fuel pool (7), connected to the cooling conduit (38) by a coupling line (42), through which a refrigerant can be circulated from the coolant reservoir, through the cooling duct, and out, to a receiving tank; a circulation mechanism (52) for circulating the refrigerant through the coupling line (42), wherein the circulation mechanism is configured to normally be in an off state in which the refrigerant does not circulate through the coupling line; a sensor (60) for monitoring a condition of the liquid within the spent fuel pool and providing a sensor output indicative of the condition; a control system (58) connected to the sensor outlet and the circulation mechanism and operable to switch on the circulation mechanism when the sensor outlet indicates that the liquid in the spent fuel pool has reached a pre-selected condition indicative of an abnormal state the condition; and including a plurality of cooling ducts connected, respectively, to the refrigerant reservoir (50), through a corresponding coupling line in parallel.
    [0002]
    Used nuclear fuel pool (7) according to claim 1, characterized by the fact that the circulation mechanism (52) is a pump powered by a primary or auxiliary power source (54).
    [0003]
    Used nuclear fuel pool (7) according to claim 2, characterized by the fact that the auxiliary power source (54) is a generator engine.
    [0004]
    Used nuclear fuel pool (7) according to claim 2, characterized by the fact that the pump (52) is a pump powered by diesel or gasoline.
    [0005]
    Used nuclear fuel pool (7) according to claim 4, characterized by the fact that the pump powered by diesel or gasoline (52) is a fire brigade truck.
    [0006]
    Used nuclear fuel pool (7) according to claim 1, characterized by the fact that the circulation mechanism (52) is an active mechanism, which is only activated when the liquid inside the used fuel pool rises above a pre-selected temperature.
    [0007]
    Used nuclear fuel pool (7) according to claim 1, characterized in that the cooling duct (38) comprises a plurality of cooling ducts connecting in parallel to the coupling line (42).
    [0008]
    Used nuclear fuel pool (7) according to claim 7, characterized by the fact that the cooling duct (38) is a plurality of cooling coils (40).
    [0009]
    Pool of used nuclear fuel (7) according to claim 1, characterized by the fact that the refrigerant is sea water.
    [0010]
    Used nuclear fuel pool (7) according to claim 1, characterized by the fact that the receiving tank (44) includes a cooling tower.
    [0011]
    Used nuclear fuel pool (7) according to claim 1, characterized by the fact that the cooling duct (38) is constructed from a copper-nickel alloy selected from the group 90/10, 70/30 or Monel.
    [0012]
    Used nuclear fuel pool (7) according to claim 1, characterized by the fact that the circulation mechanism (52) is an active mechanism, which is only activated when the liquid inside the used fuel pool reaches a pre-set level. selected.
    [0013]
    Used nuclear fuel pool (7) according to claim 1, characterized by the fact that it includes a plurality of cooling ducts (38) respectively connected to the coolant reservoir through a corresponding parallel coupling line.
    [0014]
    Used nuclear fuel pool (7) according to claim 13, characterized in that the refrigerant reservoir (50) includes a plurality of refrigerant sources and at least some of the coupling lines (47) are connected to separate some refrigerant sources.
    [0015]
    Used nuclear fuel pool (7) according to claim 13, characterized in that at least some of the cooling ducts (38) have circulation mechanisms (52) that are independent of other cooling ducts.
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    法律状态:
    2018-12-18| B06F| Objections, documents and/or translations needed after an examination request according [chapter 6.6 patent gazette]|
    2019-11-19| B06U| Preliminary requirement: requests with searches performed by other patent offices: procedure suspended [chapter 6.21 patent gazette]|
    2020-11-10| B09A| Decision: intention to grant [chapter 9.1 patent gazette]|
    2021-01-26| B16A| Patent or certificate of addition of invention granted [chapter 16.1 patent gazette]|Free format text: PRAZO DE VALIDADE: 20 (VINTE) ANOS CONTADOS A PARTIR DE 24/01/2012, OBSERVADAS AS CONDICOES LEGAIS. |
    优先权:
    申请号 | 申请日 | 专利标题
    US201161469184P| true| 2011-03-30|2011-03-30|
    US61/469184|2011-03-30|
    US13/291,334|US9847148B2|2011-03-30|2011-11-08|Self-contained emergency spent nuclear fuel pool cooling system|
    US13/291334|2011-11-08|
    PCT/US2012/022308|WO2012134611A1|2011-03-30|2012-01-24|Self-contained emergency spent nuclear fuel pool cooling system|
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