Steam line break analysis using RELAP5/MOD3.3 for steam generator blowdown load assessment / prepared by Han-Sik Jung [and four others].
- Physical Description: 1 online resource (xi, 29 pages) : illustrations (some color).
- Publisher: Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, May 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)."
|Bibliography, etc. Note:||
Includes bibliographical references (page 29).
|Type of Report and Period Covered Note:||
|Source of Description Note:||
Description based on online resource; title from PDF title page (viewed on July 11, 2017).
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|Subject:||Nuclear power plants > Piping > Safety measures.
Nuclear reactors > Cooling > Safety measures.
Nuclear power plants > United States.
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