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Assessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP5 / prepared by Andrew Oussoren, J. Riznic, S.T. Revankar.

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Format:
Book
Government document
Author/Creator:
Oussoren, Andrew, author.
Riznic, Jovica R., author.
Revankar, Shripad, author.
Contributor:
U.S. Nuclear Regulatory Commission. Division of Systems Analysis, issuing body.
Series:
International agreement report ; NUREG/IA-0457.
International agreement report ; NUREG/IA-0457
Language:
English
Subjects (All):
Pressurized water reactors--Loss of coolant.
Pressurized water reactors.
Nuclear power plants--Piping--Cracking.
Nuclear power plants.
Genre:
Online resources.
Physical Description:
1 online resource (xv, 29 pages) : illustrations (some color)
Place of Publication:
Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2017.
Notes:
"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)."
Includes bibliographical references (page 29).
Online resource; title from PDF title page (NRC, viewed March 20, 2018).
Other Format:
Print version: Oussoren, Andrew. Assessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP5
OCLC:
1029057502

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