5 results about "Decay heat" patented technology

A container for transporting a reactor is disclosed. The container includes a loop thermosiphon including a chamber, a heat exchanger fluidically coupled to the chamber, and an actuator including an unactuated state and an actuated state. The actuator is configured to automatically transition to the actuated state. The transition is based on an event occurring within the reactor. A working medium is configured to remove heat from the reactor in the actuated state.

The present application relates to the technical field of spent fuel storage, and discloses a spent fuel dry storage vault, which comprises a top air inlet vertical shaft for introducing natural ventilation, a bottom air chamber in communication with the air inlet vertical shaft, a storage chamber above the bottom air chamber, a plurality of shafts arranged in the storage chamber in a vertical direction, a heat generating body sleeved in the shafts in a spaced manner, an annular gap formed between the shafts and the heat generating body, the heat generating body containing spent fuel, the bottom air chamber in communication with a top air chamber through the annular gap, and an air outlet vertical shaft in communication with the top air chamber. Air for natural ventilation enters the air inlet vertical shaft through an air inlet, then enters the bottom air chamber, and then flows into the annular gap and the top air chamber, and is discharged from an air outlet through the air outlet vertical shaft, so that the flow path of the internal air is optimized, the storage chamber enhances the ventilation efficiency and heat exchange performance in a combined manner of heat conduction, convection and radiation heat exchange, the decay heat of the spent fuel in the heat generating body is discharged, and the safety and stability of the spent fuel dry storage vault are ensured.

The application discloses a high-level radioactive waste disposal pit multi-field coupling condition full cycle simulation system and a test method, and relates to the field of rock mechanics tests.The system comprises a true triaxial dynamic and static loading device, which can bear a fractured rock sample to be tested, and can move the fractured rock sample to a set position, and can apply dynamic and static loads in multiple directions to the fractured rock sample; a vertical excavation and tunneling device can realize simulation of an excavation process of dynamic disturbance drilling of the center of the fractured rock sample under a deep geostress environment; a disposal pit reaction source device is placed in the disposal pit to simulate a nuclide leakage process under conditions of decay heat release, corrosion and gas production of a high-level radioactive waste tank; and a fractured seepage control device can apply a water head difference to left and right end surfaces of the fractured rock sample in a horizontal direction through a rock sample pad to drive seepage solution to flow along original fractures in the fractured rock sample.The application can truly reproduce disposal pit full cycle disturbance effects, integrate multiple barrier coupling boundary conditions, and consider seepage influence on storage tank surface corrosion differences.

The present invention relates to a molten salt reactor system comprising a reactor vessel comprising a reactor core in an upper compartment, and one or more drain tanks situated in a lower compartment below the upper compartment, and a molten fuel salt pump, and a heat exchanger, wherein a molten fuel salt flow direction is provided in a fuel salt loop, said fuel salt loop comprising the reactor core, the one or more drain tanks, the molten fuel salt pump, and the heat exchanger, the direction of the molten fuel salt flow is from the heat exchanger towards the reactor core, wherein (a) the one or more drain tanks are located between the reactor core and the molten fuel salt pump in the molten fuel salt flow direction and the molten fuel salt pump is located between the one or more drain tanks and the heat exchanger in the molten fuel salt flow direction and the heat exchanger is located between the molten fuel salt pump and the reactor core in the molten fuel salt flow direction and the reactor core is located between the heat exchanger and the one or more drain tanks in the molten fuel salt flow direction, or (b) the molten fuel salt pump is located between the reactor core and the one or more drain tanks in the molten fuel salt flow direction and the one or more drain tanks are located between the molten fuel salt pump and the heat exchanger in the molten fuel salt flow direction and the heat exchanger is located between the one or more drain tanks and the reactor core in the molten fuel salt flow direction and the reactor core is located between the heat exchanger and the molten fuel salt pump in the molten fuel salt flow direction, wherein the lower compartment is provided with a passive decay heat removal system.

The embodiments of this application relate to the field of nuclear reactor monitoring, and particularly to a method for determining the power of heat generated by the decay of spent fuel assemblies in a sodium-cooled fast reactor. The method includes the following steps: S10: placing the spent fuel assembly of the sodium-cooled fast reactor whose decay heat is to be determined in a measurement space; S20: placing a coolant in the measurement space, the coolant being configured to conduct away a portion of the decay heat generated by the spent fuel assembly; S30: determining the average temperature of the walls of the measurement space, determining the power of heat dissipation from the measurement space and the power of heat conducted away by the coolant; S40: determining the power of heat generated by the decay of the spent fuel assembly based on the power of heat dissipation from the measurement space and the power of heat conducted away by the coolant. This makes the decay heat power of the spent fuel assembly more accurate, reduces the uncertainty level, thereby reducing the design conservatism margin of the decay heat extraction system, and avoids safety problems such as coolant overcooling, improving reactor safety and economy.