Post-test thermal-hydraulic analysis of PKL tests F1.1 and F1.2 /

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Bibliographic Details
Author / Creator:	Freixa, J., author.
Imprint:	Washington, DC : U.S. Nuclear Regulatory Commission, October 2014.
Description:	1 online resource (73 unnumbered pages) : color illustrations.
Language:	English
Series:	International agreement report ; NUREG/IA-0417 International agreement report ; NUREG/IA-0417.
Subject:	Nuclear power plants -- Accidents -- Computer simulation. Nuclear power plants -- Computer programs -- Testing. Pressurized water reactors -- Loss of coolant -- Computer simulation. Nuclear reactor accidents -- Computer simulation. Nuclear reactor accidents -- 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/10297407

Hidden Bibliographic Details
Other authors / contributors:	U.S. Nuclear Regulatory Commission, issuing body. U.S. Nuclear Regulatory Commission. Division of Systems Analysis, sponsoring body.
Notes:	Title from title screen (viewed April 8, 2015). "Manuscript completed: April 2011 ; Date published: October 2014." Includes bibliographical references (page 7-1). Technical report.
Other form:	Print version: Post-test thermal-hydraulic analysis of PKL tests F1.1 and F1.2
GPO item no.:	1051-H-41 (online)
Govt.docs classification:	Y 3.N 88:53/0417

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