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 /

Bibliographic Details
Main Authors:	Vinogradov, V. A. (Author), Balykin, A. Y. (Author)
Format:	Government Document eBook
Language:	English
Published:	Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, July 2002.
Series:	International agreement report ; NUREG/IA-0208.
Subjects:	Pressurized water reactors > Loss of coolant > Computer simulation.
Online Access:	https://purl.fdlp.gov/GPO/gpo84605

Available Online