Assessment of RELAP5/MOD3.2 using LOFT large break LOCA test, LP-02-6 / prepared by T.S. Choi [and seven others].
- 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.
"Korea Nuclear Fuel Company."
"Korea Institute of Nuclear Safety, Advanced Reactor Dept."
"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:||
|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).
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|Subject:||Pressurized water reactors > Loss of coolant > Computer simulation.
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