Rod bundle heat transfer test facility description /

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Bibliographic Details
Imprint:	Washington, D.C. : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2010]
Description:	1 online resource ([209] p.) : ill.
Language:	English
Subject:	Pressurized water reactors -- Loss of coolant. Nuclear fuel rods -- Testing. Heat -- Transmission. Heat -- Transmission. Nuclear fuel rods -- Testing. Pressurized water reactors -- Loss of coolant.
Format:	E-Resource U.S. Federal Government Document Book
URL for this record:	http://pi.lib.uchicago.edu/1001/cat/bib/8362680

Hidden Bibliographic Details
Other authors / contributors:	Rosal, E. R. U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.
Notes:	Title from PDF title screen (viewed on Mar. 23, 2011). "Manuscript completed: April 2008. Date published: July 2010." "NUREG/CR-6976." Includes bibliographical references. Technical report. Nov. 1997-Feb. 2003. NRC job code W6855
Other form:	Print version: Rod bundle heat transfer test facility description
GPO item no.:	1051-H-11 (online)
Govt.docs classification:	Y 3.N 88:25/CR-6976

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