SCDAP/RELAP5 independent peer review
SCDAP/RELAP5 independent peer review
The SCDAP/RELAP5 code has been developed for best-estimate transient simulation of light-water-reactor coolant systems during severe accidents. The newest version of the code is SCDAP/RELAP5/MOD3. The US Nuclear Regulatory Commission (NRC) decided that there was a need for a broad technical review of the code by recognized experts to determine overall technical adequacy, even though the code is still under development. For this purpose, an eight-member SCDAP/RELAP5 Peer Review Committee was organized, and the outcome of the review should help the NRC prioritize future code-development activity. Because the code is designed to be mechanistic, the Committee used a higher standard for technical adequacy than was employed in the peer review of the parametric MELCOR code. The Committee completed its review of the SCDAP/RELAP5 code, and the findings are documented in this report. Based on these findings, recommendations in five areas are provided: (1) phenomenological models, (2) code-design objectives, (3) code-targeted applications, (4) other findings, and (5) additional recommendations.
- University of North Texas United States
- Ricardo AEA (United Kingdom) United Kingdom
- Los Alamos National Laboratory United States
- Ricardo (United Kingdom) United Kingdom
Enriched Uranium Reactors, 210100 -- Power Reactors, Boiling Water Cooled, Nonbreeding, Nonboiling Water Cooled, Hydraulics, 990200 -- Mathematics & Computers, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Recommendations, Mechanics, Reactor Accidents, Transients, Evaluation, Light-Water Moderated, R Codes, 22 General Studies Of Nuclear Reactors, Reactor Safety, Computer Codes, Design Basis Accidents, S Codes, Computing, Pwr Type Reactors, Thermal Reactors, Heat Transfer, Bwr Type Reactors, Reactors, 99 General And Miscellaneous//Mathematics, Power Reactors, Energy Transfer, Accidents, And Information Science, Water Cooled Reactors, 210200 -- Power Reactors, Safety, Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety
Enriched Uranium Reactors, 210100 -- Power Reactors, Boiling Water Cooled, Nonbreeding, Nonboiling Water Cooled, Hydraulics, 990200 -- Mathematics & Computers, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Recommendations, Mechanics, Reactor Accidents, Transients, Evaluation, Light-Water Moderated, R Codes, 22 General Studies Of Nuclear Reactors, Reactor Safety, Computer Codes, Design Basis Accidents, S Codes, Computing, Pwr Type Reactors, Thermal Reactors, Heat Transfer, Bwr Type Reactors, Reactors, 99 General And Miscellaneous//Mathematics, Power Reactors, Energy Transfer, Accidents, And Information Science, Water Cooled Reactors, 210200 -- Power Reactors, Safety, Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety
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