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
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.
- Washington DC Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission [2001]
- 1 v. (various pagings), ill.
- International agreement report NUREG/IA-0202 .
"April 2001." "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)." Paper version no longer available for sale by the Supt. of Docs. Shipping list no.: 2001-0397-M.
Includes bibliographical references (p. 28).
Technical.
Pressurized water reactors--Loss of coolant
621.4834 ANA 2001
1051-H-41 (MF)
Y 3.N 88:53/0202
"April 2001." "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)." Paper version no longer available for sale by the Supt. of Docs. Shipping list no.: 2001-0397-M.
Includes bibliographical references (p. 28).
Technical.
Pressurized water reactors--Loss of coolant
621.4834 ANA 2001
1051-H-41 (MF)
Y 3.N 88:53/0202
