Rod bundle heat transfer test facility test plan and design /

Bibliographic Details
Corporate Author:	U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Other Authors:	Hochreiter, L. E.
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/gpo5389

Available Online