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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].

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Record details

  • 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.

Content descriptions

General Note:
"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:
Technical report.
Source of Description Note:
Description based on online resource; title from PDF title page (viewed on July 11, 2017).
Subject: Nuclear power plants > Piping > Safety measures.
Nuclear reactors > Cooling > Safety measures.
Nuclear power plants > United States.

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