Assessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP5 /

Bibliographic Details
Main Authors:	Oussoren, Andrew (Author), Riznic, Jovica R. (Author), Revankar, Shripad (Author)
Format:	Government Document eBook
Language:	English
Published:	Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2017.
Series:	International agreement report ; NUREG/IA-0457.
Subjects:	Pressurized water reactors > Loss of coolant. Nuclear power plants > Piping > Cracking.
Online Access:	https://purl.fdlp.gov/GPO/gpo90002 https://purl.fdlp.gov/GPO/gpo90001

Description
Item Description:	"Manuscript completed: November 2015." "Date published: August 2017." "Prepared as part of the Agreement on Research Participation and Technical Exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."
Physical Description:	1 online resource (xv, 29 pages) : illustrations (some color).
Bibliography:	Includes bibliographical references (page 29).