Analyses of KS test data on the heated rod bundle temperature behavior in RBMK-1500 core model under stop and recovery flow using RELAP5/MOD3.2 and RELAP5/MOD3.2.2 GAMMA / prepared by V.A. Vinogradov, A.Y. Balykin.
- Physical Description: 1 online resource (various pagings) : illustrations.
- Publisher: Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, April 2001.
|General Note:|| "Nuclear Reactor Institute, Russian Research Center, Kurchatov Institute."
"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Code Application and Maintenance Program (CAMP)."
"Sponsoring organization: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Bibliographic data sheet.
|Bibliography, etc. Note:|| Includes bibliographical references (page 28).
|Type of Report and Period Covered Note:|| Technical.
|Source of Description Note:|| Description based on online resource; title from PDF title page (viewed on Sept. 8, 2017).
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|Subject:||Pressurized water reactors > Loss of coolant > Computer simulation.
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