Published July 1997 | Version v1
Report Restricted

Methodology, status, and plans for development and assessment of the RELAP5 code

Creators

  • 1. Idaho National Engineering Laboratory, Idaho Falls, ID (United States)

Description

RELAP/MOD3 is a computer code used for the simulation of transients and accidents in light-water nuclear power plants. The objective of the program to develop and maintain RELAP5 was and is to provide the U.S. Nuclear Regulatory Commission with an independent tool for assessing reactor safety. This paper describes code requirements, models, solution scheme, language and structure, user interface validation, and documentation. The paper also describes the current and near term development program and provides an assessment of the code's strengths and limitations

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Additional details

Publishing Information

Imprint Title
Proceedings of the OECD/CSNI workshop on transient thermal-hydraulic and neutronic codes requirements
Imprint Pagination
824 p.
Journal Page Range
p. 20-41.
Report number
NUREG/CP--0159

Conference

Title
Organization for Economic Co-Operation and Development (OECD)/Committee on the Safety of Nuclear Installations (CSNI) workshop on transient thermal-hydraulic codes requirements.
Dates
5-8 Nov 1996.
Place
Annapolis, MD (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
29024715
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; MANUALS; MODIFICATIONS; PROGRAMMING LANGUAGES; R CODES; REACTOR ACCIDENTS; TRANSIENTS; WATER COOLED REACTORS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; DOCUMENT TYPES; REACTORS; SIMULATION

Optional Information

Secondary number(s)
NEA/CSNI/R--(97)4; CONF-961192--.