Assessment of RELAP5/MOD3.2 with the semiscale natural circulation experiment, S-NC-8B / prepared by Y.S. Bang [and three others].
- Physical Description: 1 online resource (various pagings) : illustrations.
- Publisher: Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, August 1998.
|General Note:|| "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 Assessment and Maintenance Program (CAMP)."
"S. Smith, NRC project manager"--Bibliographic data sheet.
|Bibliography, etc. Note:|| Includes bibliographical references (page 72).
|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).
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|Subject:||Pressurized water reactors > Loss of coolant > Computer simulation.
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