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
By: prepared by V.A. Vinogradov, A.Y. Balykin
Contributors: Balykin, A. Y; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research; Institut I︠A︡dernykh Reaktorov (Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut")
Series: International agreement report -- NUREG/IA-0202
Publisher: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Published: 2001
Place of publication: Washington, DC
Language: eng
Format: Microform
Subjects: Pressurized water reactors -- Loss of coolant -- Computer simulation
Notes: "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)."

Shipping list no.: 2001-0397-M

"April 2001."

Paper version no longer available for sale by the Supt. of Docs

Includes bibliographical references (p. 28)

Technical

Microfiche. [Washington, D.C.] : Supt. of Docs., U.S. G.P.O., [2001] 1 microfiche : negative