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Title: Preapplication safety evaluation report for the Power Reactor Innovative Small Module (PRISM) liquid-metal reactor. Final report

Preapplication safety evaluation report for the Power Reactor Innovative Small Module (PRISM) liquid-metal reactor. Final report This preapplication safety evaluation report (PSER) presents the results of the preapplication desip review for die Power Reactor Innovative Small Module (PRISM) liquid-mew (sodium)-cooled reactor, Nuclear Regulatory Commission (NRC) Project No. 674. The PRISM conceptual desip was submitted by the US Department of Energy in accordance with the NRC`s ``Statement of Policy for the Regulation of Advanced Nuclear Power Plants`` (51 Federal Register 24643). This policy provides for the early Commission review and interaction with designers and licensees. The PRISM reactor desip is a small, modular, pool-type, liquid-mew (sodium)-cooled reactor. The standard plant design consists of dim identical power blocks with a total electrical output rating of 1395 MWe- Each power block comprises three reactor modules, each with a thermal rating of 471 MWt. Each module is located in its own below-grade silo and is co to its own intermediate heat transport system and steam generator system. The reactors utilize a metallic-type fuel, a ternary alloy of U-Pu-Zr. The design includes passive reactor shutdown and passive decay heat removal features. The PSER is the NRC`s preliminary evaluation of the safety features in the PRISM design, including the projected research and development programs required to support the design and the proposed more » testing needs. Because the NRC review was based on a conceptual design, the PSER did not result in an approval of the design. Instead it identified certain key safety issues, provided some guidance on applicable licensing criteria, assessed the adequacy of the preapplicant`s research and development programs, and concluded that no obvious impediments to licensing the PRISM design had been identified. « less
Authors: ; ; ; ; ; ; ;
Publication Date:
OSTI Identifier:10133164
Report Number(s):NUREG--1368
ON: TI94008221; TRN: 94:008467
Resource Type:Technical Report
Resource Relation:Other Information: PBD: Feb 1994
Research Org:Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Reactor Regulation; Nuclear Regulatory Commission, Washington, DC (United States). Associate Directorate for Advanced Reactors and License Renewal
Sponsoring Org:Nuclear Regulatory Commission, Washington, DC (United States)
Country of Publication:United States
Language:English
Subject: 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; LMFBR TYPE REACTORS; DESIGN; REACTOR SAFETY; CONTAINMENT; FUEL ELEMENTS; REACTIVITY; REACTOR CONTROL SYSTEMS; AFTER-HEAT REMOVAL; SAFETY ANALYSIS; TESTING; REACTOR LICENSING; PROGRESS REPORT 210500; 220900; POWER REACTORS, BREEDING; REACTOR SAFETY