RELAP-7 User's Guide

Zhang, Hongbin¹  Zhao, Haihua¹  Zou, Ling¹  Andrs, David² 

[1] Idaho National Lab. (INL), Idaho Falls, ID (United States);Idaho National La

关键词: WATER MODERATED REACTORS;    WATER COOLED REACTORS;    SAFETY ANALYSIS;    SAFETY MARGINS;    R CODES;    SYSTEMS ANALYSIS;    REACTOR SAFETY;    COMPUTERIZED SIMULATION;    SUSTAINABILITY RELAP-7 User's Guide;   

DOI  :  10.2172/1235195
RP-ID  :  INL/EXT--14-33977
PID  :  OSTI ID: 1235195
Others  :  TRN: US1600230

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来源: SciTech Connect

【 摘 要 】

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.