Rod bundle heat transfer test facility description /

Bibliographic Details
Corporate Author:	U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Other Authors:	Rosal, E. R.
Format:	Government Document eBook
Language:	English
Published:	Washington, D.C. : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2010]
Subjects:	Pressurized water reactors > Loss of coolant. Nuclear fuel rods > Testing. Heat > Transmission.
Online Access:	https://purl.fdlp.gov/GPO/gpo5388

Description
Item Description:	Title from PDF title screen (viewed on Mar. 23, 2011). "Manuscript completed: April 2008. Date published: July 2010." "NUREG/CR-6976." Electronic resource.
Physical Description:	1 online resource (209 unnumbered pages) : illustrations
Bibliography:	Includes bibliographical references.