Feedwater line break analysis using RELAP5/MOD3.3 for steam generator blowdown load assessment /

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

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Bibliographic Details
Online Access: Online Access
Main Author: Jung, Han-Sik (Author)
Format: Government Document eBook
Language:English
Published: Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, November 2016.
Series:International agreement report ; NUREG/IA-0473.
Subjects:
Nuclear power plants > Piping > Safety measures.
Steam-boilers.
Nuclear reactors > Cooling > Safety measures.
Nuclear power plants > United States.
Description
Item Description:"Manuscript completed: February 2016; date published: November 2016."
"Doosan Heavy Industry and Construction."
"Korea Institute of Nuclear Safety."
"K. Tien, NRC project manager."
"Prepared as part of the Agreement of Research Participation and Technical Exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."
Physical Description:1 online resource (31 pages) : color illustrations.
Bibliography:Includes bibliographical references (page 31)

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