Preapplication safety evaluation report for the Power Reactor Innovative Small Module (PRISM) liquid-metal reactor. Final report
Description/Abstract
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 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.
| DOI | 10.2172/10133164 |
|---|---|
| Creator/Author: | Donoghue, J.E. ; Donohew, J.N. ; Golub, G.R. ; Kenneally, R.M. ; Moore, P.B. ; Sands, S.P. ; Throm, E.D. ; Wetzel, B.A. [Nuclear Regulatory Commission, Washington, DC (United States). Associate Directorate for Advanced Reactors and License Renewal] |
| Publication Date: | 1994 Feb 01 |
| OSTI Identifier: | OSTI ID: 10133164; Legacy ID: TI94008221 |
| Report Number(s): | NUREG--1368 |
| DOI: | 10.2172/10133164 |
| Other Number(s): | Other: ON: TI94008221 |
| Resource Type: | Technical Report |
| Specific Type: | Progress 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) |
| 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 |
| Country of Publication: | United States |
| Language: | English |
| Format: | Size: 422 p. |
| Availability: | INIS; OSTI as TI94008221; Paper copy available at OSTI: phone, 865-576-8401, or email, reports@adonis.osti.gov |
| Update Date: | 2008 Feb 12 |
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