Assessment of RELAP5/MOD3.1 using LSTF ten-percent main steam-line-break test run SB-SL-01 / prepared by J.G. Oh [and seven others].
- Physical Description: 1 online resource (viii, 111 pages) : illustrations.
- Publisher: Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, September 1998.
"Korea Power Engineering Company."
"Korea Institute of Nuclear Safety."
"Japan Atomic Energy Research Institute."
"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Maintenance Program (CAMP)."
"G. Rhee, NRC project manager"--Bibliographic data sheet.
|Bibliography, etc. Note:||
Includes bibliographical references (page 29).
|Funding Information Note:||
Sponsored by the Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission D6227
|Source of Description Note:||
Description based on online resource; title from PDF title page (viewed on July 28, 2017).
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|Subject:||Pressurized water reactors > Loss of coolant > Computer programs > Testing.
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