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Using TRACE, MELCOR, CFD, and FRAPTRAN to establish the analysis methodology for Chinshan Nuclear Power Plant spent fuel pool / prepared by Jong-Rong Wang [and nine others].

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Format:
Book
Government document
Author/Creator:
Wang, Jong-Rong, author.
Contributor:
U.S. Nuclear Regulatory Commission. Division of Systems Analysis, issuing body.
Series:
International agreement report ; NUREG/IA-0482.
International agreement report ; NUREG/IA-0482
Language:
English
Subjects (All):
Boiling water reactors--Taiwan--Evaluation.
Boiling water reactors.
Nuclear power plants--Taiwan.
Nuclear power plants.
Boiling water reactors--Taiwan--Computer simulation.
Spent reactor fuels--Storage--Taiwan.
Spent reactor fuels.
Boiling water reactors--Evaluation.
Spent reactor fuels--Storage.
Taiwan.
Physical Description:
1 online resource (xv, 33 pages) : illustrations (some color)
Place of Publication:
Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, October 2018.
Notes:
"K. Tien, NRC project manager."
"Manuscript completed: April 2017; Date published: October 2018."
"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 (page 33).
Other Format:
Print version: Wang, Jong-Rong. Using TRACE, MELCOR, CFD, and FRAPTRAN to establish the analysis methodology for Chinshan Nuclear Power Plant spent fuel pool
OCLC:
1127640197

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