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PRISM (reactor)
PRISM (Power Reactor Innovative Small Module, sometimes S-PRISM from SuperPRISM) is a nuclear power plant design by GE Vernova Hitachi Nuclear Energy (GVH).
The S-PRISM represents GVH's Generation IV reactor solution to closing the nuclear fuel cycle and is also part of its Advanced Recycling Center (ARC) proposition to the U.S. Congress to deal with nuclear waste. S-PRISM is a commercial implementation of the Integral Fast Reactor developed by Argonne National Laboratory between 1984 and 1994.
It is a sodium-cooled fast breeder reactor, based on the Experimental Breeder Reactor II (EBR-II) design, scaled up by a factor of ten.
The design utilizes reactor modules, each having a power output of 311 MWe, to enable factory fabrication at low cost.
In an identical fashion to the EBR-II that it is based on, the reactor would transition to a much lower power level whenever temperatures rise significantly, moreover the reactor vessel modules are pool type, as opposed to loop type, with the pool conferring substantial thermal inertia and the final key safety feature includes a "RVACS", which is a passive reactor vessel air cooling system to remove decay heat. These safety systems are passive and therefore always operate and are to prevent core damage when no other means of heat removal are available.
As of 2022, the PRISM design is not under active consideration.
The integral fast reactor was developed at the West Campus of the Argonne National Laboratory in Idaho Falls, Idaho and was an extension (inc fuel reprocessing) to the Experimental Breeder Reactor II, which achieved first criticality in 1965 and ran for 30 years. The Integral Fast Reactor project (and EBR II) was shut down by the U.S. Congress in 1994. GE-Hitachi (GEH) continued work on the concept until 2001.
In October 2010, GEH signed a memorandum of understanding with the operators of the Department of Energy's (DOE) Savannah River site, which should allow the construction of a demonstration reactor prior to the design receiving full NRC licensing approval.
Hub AI
PRISM (reactor) AI simulator
(@PRISM (reactor)_simulator)
PRISM (reactor)
PRISM (Power Reactor Innovative Small Module, sometimes S-PRISM from SuperPRISM) is a nuclear power plant design by GE Vernova Hitachi Nuclear Energy (GVH).
The S-PRISM represents GVH's Generation IV reactor solution to closing the nuclear fuel cycle and is also part of its Advanced Recycling Center (ARC) proposition to the U.S. Congress to deal with nuclear waste. S-PRISM is a commercial implementation of the Integral Fast Reactor developed by Argonne National Laboratory between 1984 and 1994.
It is a sodium-cooled fast breeder reactor, based on the Experimental Breeder Reactor II (EBR-II) design, scaled up by a factor of ten.
The design utilizes reactor modules, each having a power output of 311 MWe, to enable factory fabrication at low cost.
In an identical fashion to the EBR-II that it is based on, the reactor would transition to a much lower power level whenever temperatures rise significantly, moreover the reactor vessel modules are pool type, as opposed to loop type, with the pool conferring substantial thermal inertia and the final key safety feature includes a "RVACS", which is a passive reactor vessel air cooling system to remove decay heat. These safety systems are passive and therefore always operate and are to prevent core damage when no other means of heat removal are available.
As of 2022, the PRISM design is not under active consideration.
The integral fast reactor was developed at the West Campus of the Argonne National Laboratory in Idaho Falls, Idaho and was an extension (inc fuel reprocessing) to the Experimental Breeder Reactor II, which achieved first criticality in 1965 and ran for 30 years. The Integral Fast Reactor project (and EBR II) was shut down by the U.S. Congress in 1994. GE-Hitachi (GEH) continued work on the concept until 2001.
In October 2010, GEH signed a memorandum of understanding with the operators of the Department of Energy's (DOE) Savannah River site, which should allow the construction of a demonstration reactor prior to the design receiving full NRC licensing approval.
