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DOE OSTI · 1235195

RELAP-7 User's Guide

Zhang, Hongbin·Zhao, Haihua·Zou, Ling·Andrs, David·Berry, Ray Alden·Martineau, Richard Charles
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Abstract

The document contains a user's guide on how to run the RELAP-7 code. The RELAP-7 code is the next generation nuclear reactor system safety analysis code being developed at the Idaho National Laboratory. RELAP-7 will become the main reactor systems simulation toolkit for the LWRS (Light Water Reactor Sustainability) program’s RISMC (Risk Informed Safety Margin Characterization) effort and the next generation tool in the RELAP reactor safety/systems analysis application series. RELAP-7 is written with object oriented programming language C++. A number of example problems and their associated input files are presented in this document to guide users to run the RELAP-7 code starting with simple pipe problems to problems with increasing complexity.

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS97 MATHEMATICS AND COMPUTINGCOMPUTERIZED SIMULATIONR CODESREACTOR SAFETYRELAP-7 User's GuideSAFETY ANALYSISSAFETY MARGINSSUSTAINABILITYSYSTEMS ANALYSISWATER COOLED REACTORSWATER MODERATED REACTORS

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Zhang, Hongbin, Zhao, Haihua, Zou, Ling, Andrs, David, Berry, Ray Alden, Martineau, Richard Charles. 2014-12-01. RELAP-7 User's Guide. https://doi.org/10.2172/1235195

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