Analysis of the VTI test data on the behavior of the heated rod temperatures in the partially uncovered VVER-440 core model using RELAP5/MOD3.2.2 gamma / prepared by V.A. Vinogradov, and A.Y. Balykin.
- Physical Description: 1 online resource (various pagings) : illustrations.
- Publisher: Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, July 2002.
"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)."
|Bibliography, etc. Note:||
Includes bibliographical references (page 48).
|Type of Report and Period Covered Note:||
|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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