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Assessment of RELAP5/MOD3.2 using LOFT large break LOCA test, LP-02-6 / prepared by T.S. Choi [and seven others].

Record details

  • Physical Description: 1 online resource (vi, 68 pages, A38 pages) : illustrations.
  • Publisher: Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, August 1998.

Content descriptions

General Note: "Korea Nuclear Fuel Company."
"Korea Institute of Nuclear Safety, Advanced Reactor Dept."
"August 1998."
"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Maintenance Program (CAMP)."
"S. Smith, NRC project manager"--Bibliographic data sheet.
Bibliography, etc. Note: Includes bibliographical references.
Type of Report and Period Covered Note: Technical report.
Funding Information Note: Sponsored by the Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission W6238
Source of Description Note: Description based on online resource; title from PDF title page (viewed on July 21, 2017).
Subject: Pressurized water reactors > Loss of coolant > Computer simulation.

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