2 options
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 six others].
- Format:
- Book
- Government document
- Author/Creator:
- Shih, Chunkuan, author.
- Series:
- International agreement report ; NUREG/IA-0465.
- International agreement report ; NUREG/IA-0465
- Language:
- English
- Subjects (All):
- Nuclear power plants--Taiwan.
- Nuclear power plants.
- Nuclear fuel rods--Thermal properties--Computer programs.
- Nuclear fuel rods.
- Taiwan.
- Physical Description:
- 1 online resource ([93] pages) : color illustrations.
- Place of Publication:
- Washington, DC : U.S. Nuclear Regulatory Commission, March 2016.
- Notes:
- Title from title screen (viewed on Mar. 31, 2016).
- "Manuscript completed: August 2015; Date published: March 2016."
- Includes bibliographical references (pages 6-1).
- "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."
- Other Format:
- Print version: Shih, Chunkuan. Fuel rod performance uncertainty analysis during overpressurization transient for Kuosheng Nuclear Power Plant with TRACE/FRAPTRAN/Dakota codes in SNAP interface
- OCLC:
- 945968996
The Penn Libraries is committed to describing library materials using current, accurate, and responsible language. If you discover outdated or inaccurate language, please fill out this feedback form to report it and suggest alternative language.