Fuel rod behavior and uncertainty analysis by FRAPTRAN/TRACE/DAKOTA code in maanshan LBLOCA / prepared by Chunkuan Shih [and five others].
- Physical Description: 1 online resource (various pagings) : illustrations.
- Publisher: Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, August 2016.
|General Note:|| Title from title screen (viewed Aug. 26, 2016).
"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)."
|Bibliography, etc. Note:|| Includes bibliographical references.
|Type of Report and Period Covered Note:|| Technical.
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|Subject:||Nuclear fuel rods > Thermal properties > Computer programs.
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