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Steam line break analysis using RELAP5/MOD3.3 for steam generator blowdown load assessment / prepared by Han-Sik Jung [and four others].

Author/Creator:
Jung, Han-Sik, author.
Publication:
Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, May 2017.
Format/Description:
Government document
Book
1 online resource (xi, 29 pages) : illustrations (some color).
Series:
International agreement report ; NUREG/IA-0474.
International agreement report ; NUREG/IA-0474
Status/Location:
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Subjects:
Nuclear power plants -- Piping -- Safety measures.
Steam-boilers.
Nuclear reactors -- Cooling -- Safety measures.
Nuclear power plants -- United States.
Notes:
Description based on online resource; title from PDF title page (viewed on July 11, 2017).
"Korea Institute of Nuclear Safety."
"K. Tien, NRC project manager."
"Manuscript completed: February 2016; date published: May 2017."
"Prepared as part of the Agreement of Research Participation and Technical Exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."
GPO Cataloging Record Distribution Program (CRDP).
Includes bibliographical references (page 29).
Contributor:
U.S. Nuclear Regulatory Commission. Division of Systems Analysis. issuing body.
Other format:
Print version: Jung, Han-Sik. Steam line break analysis using RELAP5/MOD3.3 for steam generator blowdown load assessment
OCLC:
1001433822