Item Details

Fuel Rod Behavior and Uncertainty Analysis by FRAPTRAN/TRACE/DAKOTA Code in Maanshan LBLOCA

prepared by Chunkuan Shih [and five others]
Format
EBook; Book; Government Document; Online
Published
Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, August 2016.
Language
English
Series
International Agreement Report
SuDoc Number
Y 3.N 88:53/0471
Description
1 online resource (various pagings) : illustrations.
Notes
  • "Institute of Nuclear Engineering and Science, National Tsing Hua University, Nuclear and New Energy Education and Research Foundation."
  • "Department of Nuclear Safety, Taiwan Power Company."
  • "K. Tien, NRC project manager."
  • "Manuscript completed: March 2016; date published: August 2016."
  • "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.
Series Statement
International agreement report ; NUREG/IA-0471
International agreement report NUREG/IA-0471
Logo for Copyright Not EvaluatedCopyright Not Evaluated
Technical Details
  • Access in Virgo Classic

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    a| Nuclear reactor accidents x| Analysis.
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    a| Pressurized water reactors x| Loss of coolant x| Analysis.
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