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.
|General Note:|| "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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