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
By: prepared by V.A. Vinogradov and A.Y. Balykin
Contributors: Balykin, A. Y; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research; Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut."
Series: International agreement report -- NUREG/IA-0208
Publisher: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission; Supt. of Docs., U.S. G.P.O. [distributor
Published: 2002
Place of publication: Washington, DC
Language: eng
Format: Microform
Subjects: Pressurized water reactors -- Loss of coolant -- Computer simulation
Notes: "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.: 2003-0089-M

"July 2002."

Includes bibliographical references (p. 48)

Technical

Microfiche. [Washington, D.C.] : Supt. of Docs., U.S. G.P.O., [2003] 2 microfiches : negative