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Fuel rod behavior and uncertainty analysis by FRAPTRAN/TRACE/DAKOTA code in maanshan LBLOCA / prepared by Chunkuan Shih [and five others].
Connect to full text Available online
View online- Format:
- Book
- Government document
- Author/Creator:
- Shih, Chunkuan, author.
- Series:
- International agreement report ; NUREG/IA-0471.
- International agreement report ; NUREG/IA-0471
- Language:
- English
- Subjects (All):
- Nuclear fuel rods.
- Nuclear reactor accidents--Analysis.
- Nuclear reactor accidents.
- Pressurized water reactors--Loss of coolant--Analysis.
- Pressurized water reactors.
- Nuclear power plants--Taiwan.
- Nuclear power plants.
- Taiwan.
- Physical Description:
- 1 online resource (various pagings) : illustrations.
- Place of Publication:
- Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, August 2016.
- Notes:
- Online resource; title from PDF title page (viewed on 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)."
- Includes bibliographical references.
- Other Format:
- Print version: Shih, Chunkuan. Fuel rod behavior and uncertainty analysis by FRAPTRAN/TRACE/DAKOTA code in maanshan LBLOCA
- OCLC:
- 957772481
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