An emergency spent nuclear fuel pool cooling system that requires no external electrical power source and relies on the expansion of a cryogenic fluid through an evaporator/heat exchanger submerged within the spent fuel pool, to power various components used to cool the spent fuel pool and adjacent areas and provide makeup water to the spent fuel pool. Other than the evaporator/heat exchanger to which the cryogenic fluid is connected, the remaining components employed to cool the pool and the surrounding area and provide makeup water can be contained in a relatively small, readily transportable skid.

A heat pipe based passive residual heat removal system for a spent fuel pool (3). Partitions (6) are arranged around an inside of the spent fuel pool. Evaporation-end heat pipes (4) are arranged between the outside of the partitions and an inner wail of the pool. The evaporation-end heat pipes have outlets that extend beyond the pool and are connected to an Inlet of an ascending pipe (10), and have inlets connected to an outlet of a descending pipe (5). Condensation-end heat pipes (7) have inlets connected to an outlet of the ascending pipe, and have outlets connected to an inlet of the descending pipe. The heat pipes cool the spent fuel pool. A heat exchange by phase change of working medium in the heat pipe leads to heat exchange of low temperature difference and high efficiency, relying on density difference for natural circulation drive.

A heat pipe based passive residual heat removal system for a spent fuel pool (3). Partitions (6) are arranged around an inside of the spent fuel pool. Evaporation-end heat pipes (4) are arranged between the outside of the partitions and an inner wail of the pool. The evaporation-end heat pipes have outlets that extend beyond the pool and are connected to an Inlet of an ascending pipe (10), and have inlets connected to an outlet of a descending pipe (5). Condensation-end heat pipes (7) have inlets connected to an outlet of the ascending pipe, and have outlets connected to an inlet of the descending pipe. The heat pipes cool the spent fuel pool. A heat exchange by phase change of working medium in the heat pipe leads to heat exchange of low temperature difference and high efficiency, relying on density difference for natural circulation drive.

A method for storing nuclear fuel includes transferring a fuel assembly from a long term storage vault to a nuclear reactor core, removing the fuel assembly from the nuclear reactor core, determining a heat generation rate of the irradiated fuel assembly, and transferring the irradiated fuel assembly to one of an interim storage vault and a long term storage vault based on the determined heat generation rate.

A method for storing nuclear fuel includes transferring a fuel assembly from a long term storage vault to a nuclear reactor core, removing the fuel assembly from the nuclear reactor core, determining a heat generation rate of the irradiated fuel assembly, and transferring the irradiated fuel assembly to one of an interim storage vault and a long term storage vault based on the determined heat generation rate.

A nuclear facility includes a fuel element pool which is filled with a cooling liquid. A fuel element rack, which is disposed in the fuel element pool, includes compartments for receiving fuel elements. The fuel elements received in the compartments are in direct contact with the cooling liquid in the fuel element pool. At least one cooling element is disposed in one of the compartments instead of a fuel element. The cooling element acts as a heat exchanger through which a coolant can flow, the cooling element is connected into a cooling circuit and the cooling element is immersed in the cooling liquid.

A fuel salt shipping system includes an outer container defining an outer containment volume and an inner container disposed within the outer containment volume, with the inner container defining an inner volume configured to contain a molten fuel salt. The inner container and the outer container cooperate to define an annulus region therebetween. The fuel salt shipping system further includes a fuel salt conduit penetrating the outer container and the inner container and fluidically coupling the inner volume to an external environment of the system. The fuel salt shipping system further includes a heating system including a heater disposed in the annulus space and configured to impart a heat output to the molten fuel salt of the inner volume and change a phase of the molten fuel salt held therein from a solid phase to a liquid phase.

A method of handling spent nuclear fuel assemblies immerses the spent nuclear fuel assemblies in water in a relatively short time period when compared to traditional methods. A spent nuclear fuel assembly is removed from a nuclear reactor, an inert gas is applied to the fuel assembly, moisture content in the inert gas is gradually increased as it is applied to the fuel assembly, and the fuel assembly is immersed in water. The fuel assembly is immersed relatively quickly, within about 2 hours or less, which improves safety and allows normal processing and handling equipment to care for the fuel assembly. The fuel assembly may then be loaded into a cask for long-term storage and/or disposal.

A passively-cooled spent nuclear fuel pool system comprising a spent nuclear fuel pool having a body of liquid water having a surface level. Spent nuclear fuel is submerged in the body of liquid water. The spent fuel heats the body of liquid water and produces water vapor. A lid covering the spent nuclear fuel pool to form a hermetically sealed vapor space between the surface level of the body of liquid water and the lid. A passive heat exchange sub-system fluidly comprising at least one riser conduit and at least one downcomer conduct is coupled to the vapor space. The passive heat exchange sub-system is configured to move water vapor and condensed water vapor via a thermosiphon flow.

A passively-cooled spent nuclear fuel pool system comprising a spent nuclear fuel pool having a body of liquid water having a surface level. Spent nuclear fuel is submerged in the body of liquid water. The spent fuel heats the body of liquid water and produces water vapor. A lid covering the spent nuclear fuel pool to form a hermetically sealed vapor space between the surface level of the body of liquid water and the lid. A passive heat exchange sub-system fluidly comprising at least one riser conduit and at least one downcomer conduct is coupled to the vapor space. The passive heat exchange sub-system is configured to move water vapor and condensed water vapor via a thermosiphon flow.