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

Description
Item Description:	Title from title screen (viewed Oct. 25, 2013). "September 2013."
Physical Description:	1 online resource (xiii, 29 pages) : color illustrations.
Bibliography:	Includes bibliographical references (page 29).