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Assessment of RELAP5/MOD2 code using loss of offsite power transient data of KNU #1 plant / prepared by Bud-Dong Chung, Hho-Jung Kim, Young-Jin Lee.
Author
Chung, Bud-Dong
[Browse]
Format
Book
Language
English
Published/Created
Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, April 1990.
Description
1 online resource (v, 89 pages) : illustrations.
Availability
Available Online
Marcive GPO Government Documents
Details
Subject(s)
Pressurized water reactors
—
Safety measures
—
Computer programs
[Browse]
Transients (Dynamics)
—
Computer programs
[Browse]
Author
Kim, H. J. (Hho Jung)
[Browse]
Lee, Young Jin
[Browse]
Issuing body
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
[Browse]
Series
International agreement report ; NUREG/IA-0030.
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Notes
"Nuclear Safety Center, Korea Advanced Energy Research Institute."
"Department of Nuclear Engineering, Seoul National University."
"April 1990."
"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP)."
"Technical"--Bibliographic data sheet.
Bibliographic references
Includes bibliographical references (page 34).
Source of description
Description based on online resource; title from PDF title page (viewed on Oct. 7, 2016).
SuDoc no.
Y 3.N 88:53/0030
Statement on language in description
Princeton University Library aims to describe library materials in a manner that is respectful to the individuals and communities who create, use, and are represented in the collections we manage.
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