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

Bibliographic Details
Main Author:	Freixa, J. (Author)
Corporate Author:	U.S. Nuclear Regulatory Commission. Division of Systems Analysis (sponsoring body.)
Format:	Government Document eBook
Language:	English
Published:	Washington, DC : U.S. Nuclear Regulatory Commission, October 2014.
Series:	International agreement report ; NUREG/IA-0417.
Subjects:	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.
Online Access:	https://purl.fdlp.gov/GPO/gpo56256 http://purl.fdlp.gov/GPO/gpo56256

Description
Item Description:	Title from title screen (viewed April 8, 2015). "Manuscript completed: April 2011 ; Date published: October 2014."
Physical Description:	1 online resource (73 unnumbered pages) : color illustrations.
Bibliography:	Includes bibliographical references (page 7-1).