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Fuel rod performance uncertainty analysis during overpressurization transient for Kuosheng Nuclear Power Plant with TRACE/FRAPTRAN/Dakota codes in SNAP interface / prepared by Chunkuan Shih [and aix others].

Record details

  • Physical Description: 1 online resource (93 unnumbered pages) : color illustrations.
  • Publisher: Washington, DC : U.S. Nuclear Regulatory Commission, March 2016.

Content descriptions

General Note: Title from title screen (viewed on Mar. 31, 2016).
"Manuscript completed: August 2015; Date published: March 2016."
"Prepared as part of The technical exchange and cooperation between the U.S. Nuclear Regulatory Commission and the Task Force for Safety Critical Software in the Field of Nuclear Safety Research."
Bibliography, etc. Note: Includes bibliographical references (page 6-1).
Subject: Nuclear power plants > Taiwan.
Nuclear fuel rods > Thermal properties > Computer programs.

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