摘要:
Disclosed is a decay heat removal system for cooling the decay heat of a reactor core and the spent fuel. The decay heat removal system including: a first heat pipe which is placed in an upper plenum of the reactor vessel and arranged in upward and downward directions corresponding to a position of an insertion hole formed on a top of the nuclear fuel assemblies; a control rod drive mechanism which is connected to an upper portion of the first heat pipe and drives the first heat pipe to move up and down so that the first heat pipe can be selectively inserted in a control rod insertion hole of the reactor core arranged in the nuclear reactor vessel; and a second heat pipe which is coupled to and in close contact with a bottom surface of the reactor vessel and removes the decay heat generated in the reactor core.
摘要:
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.
摘要:
A device for the electrical heating of a liquid with high thermal flow, according to which the resistor in tubular form and supplied with direct current can indirectly heat the liquid by conduction through an electrically insulating and thermally conductive intermediate element that surrounds it with direct mechanical contact, the assembly consisting of tubular resistor and intermediate element being jacketed by a sheath intended to be immersed, over at least a major part of the length thereof, in the liquid to be heated. The preferred application is the electrical simulation of nuclear fuel rods intended to be assembled in power reactors, of the PWR but also RNR-Na type.
摘要:
An autonomous facility for storing spent nuclear fuel in one embodiment includes a building forming an enclosed interior space containing a water-filled spent fuel pool. The pool includes fuel racks containing spent fuel assemblies which heat the water via radioactive decay. A passive cooling system includes a submerged heat exchanger in the pool and an air cooled heat exchanger located in ambient air outside the building at a higher elevation than the pool heat exchanger. A heat transfer working fluid circulates in a closed flow loop between the heat exchangers via unpumped natural gravity driven flow to cool the fuel pool. The air cooled heat exchanger may be enclosed in a concrete reinforced silo adjoining the building for impact protection. The building may include a cask pit formed integrally with the pool to allow fuel assembles to be removed from a transport cask and loaded into the fuel rack underwater.
摘要:
A fuel element storage and cooling configuration includes a fuel element storage pool and a cooling system having at least one first heat exchanger disposed in the fuel element storage pool and at least one second heat exchanger disposed in a heat sink and located at a distance therefrom, above a highest point of the first heat exchanger. The two heat exchangers are connected, using a pipe system, to form a closed circuit, which is at least partially filled with a flowable coolant. If the temperature of the first heat exchanger is increased with respect to the second heat exchanger, natural circulation of the coolant, and thus heat transport from the fuel element storage pool to the heat sink, is ensured without a pump apparatus.
摘要:
A transport/storage container holding spent radioactive fuel elements is cooled by withdrawing gases from inside the container to create a subatmospheric pressure therein, feeding coolant water from a reservoir into the container, withdrawing steam from the container, and condensing the steam outside the container into condensate water. A common pump is used both to withdraw gases and steam from the container. The steam is condensed by contacting it with water drawn from the reservoir. In addition the water drawn from the reservoir is passed countercurrent to the steam in a condenser and the condensate water is fed back to the reservoir.
摘要:
A horizontal, modular, dry, irradiated fuel storage system (10) includes a thin-walled canister (12) for containing irradiated fuel assemblies (20), which canister (12) can be positioned in a transfer cask (14) and transported in a horizontal manner from a fuel storage pool (18), to an intermediate-term storage facility. The storage system (10) includes a plurality of dry storage modules (26) which accept the canister (12) from the transfer cask (14) and provide for appropriate shielding about the canister (12). Each module (26) also provides for air cooling of the canister (12) to remove the decay heat of the irradiated fuel assemblies (20). The modules (26) can be interlocked so that each module (26) gains additional shielding from the next adjacent module (26). Hydraulic rams (30) are provided for inserting and removing the canisters (12) from the modules (26).
摘要:
The invention relates to a handling system for nuclear fuel assemblies. The system comprises a trough on the base of a tank which is filled with sodium. The trough is open at its top and has a seating for receiving a fuel assembly. The system also includes a bell-shaped member which is open at the bottom and is provided with means for temporarily locking the bell-shaped member to the trough in a position over the fuel assembly. A Utube connects the closed top of the bell-shaped member to the exterior and the trough is provided with a siphon device for emptying the trough.