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.
|General Note:|| "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:|| Technical.
|Source of Description Note:|| Description based on online resource; title from PDF title page (viewed on Sept. 8, 2017).
Search for related items by subject
|Subject:||Pressurized water reactors > Loss of coolant > Computer simulation.
Search for related items by series