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 /

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Bibliographic Details
Author / Creator:	Vinogradov, V. A., author.
Imprint:	Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, April 2001.
Description:	1 online resource (various pagings) : illustrations.
Language:	English
Series:	International agreement report ; NUREG/IA-0202 International agreement report ; NUREG/IA-0202.
Subject:	Pressurized water reactors -- Loss of coolant -- Computer simulation. Pressurized water reactors -- Loss of coolant -- Computer simulation.
Format:	E-Resource U.S. Federal Government Document Book
URL for this record:	http://pi.lib.uchicago.edu/1001/cat/bib/11547474

Hidden Bibliographic Details
Other authors / contributors:	Balykin, A. Y., author. U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, issuing body.
Notes:	"Nuclear Reactor Institute, Russian Research Center, Kurchatov Institute." "April 2001." "Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Code Application and Maintenance Program (CAMP)." "Sponsoring organization: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Bibliographic data sheet. Includes bibliographical references (page 28). Technical. Description based on online resource; title from PDF title page (viewed on Sept. 8, 2017).
Other form:	Microfiche version: Vinogradov, V. A. 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.
GPO item no.:	1051-H-41 (online)
Govt.docs classification:	Y 3.N 88:53/0202

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