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

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