The Power Reactor Innovative Small Module (PRISM) is a small modular sodium-cooled fast reactor (SFR) design developed by GE Hitachi Nuclear Energy (GEH), and based on the the Integral Fast Reactor. With a thermal power rating of 840 MWth and an electrical output of 311 MWe, PRISM uses metallic fuel immersed in a liquid sodium bath at atmospheric pressure. It features inherent safety measures, including passive heat removal, negative power reactivity feedback, and a large in-vessel coolant inventory.
PRISM's design stems from historical liquid-metal reactor concepts, with precedents like the Experimental Breeder Reactors I and II. The U.S. Nuclear Regulatory Commission identified no significant obstacles to licensing PRISM, which could recycle used nuclear fuel and weapons-grade materials. It was selected for the Versatile Test Reactor program at Idaho National Lab, but after that program was scrapped due to lack of funding, all formal consideration of building the PRISM ceased.
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