Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE /

Bibliographic Details
Main Authors:	Belaïd, S. (Author), Freixa, J. (Author), Zerkak, O. (Author)
Format:	Government Document eBook
Language:	English
Published:	Washington, DC : U.S. Nuclear Regulatory Commission, 2013.
Series:	International agreement report ; NUREG/IA-0432.
Subjects:	Pressurized water reactors > Testing. Emergency core cooling systems > Testing. Pressurized water reactors > Equipment and supplies > Effect of temperature on > Measurement. Nuclear fuel claddings > Effect of temperature on > Measurement. Nuclear power plants > Safety measures > Testing.
Online Access:	https://purl.fdlp.gov/GPO/gpo40912 http://purl.fdlp.gov/GPO/gpo40912

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