An analysis of semiscale Mod-2C S-FS-1 steam line break test using RELAP5/MOD2
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Author
Contributions
- United Kingdom Atomic Energy Authority. - Contributor
- U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. - Contributor
Publication
1992 - U.S. Nuclear Regulatory Commission, Washington, DC, District of Columbia
Language
English
Word Count
9,750 words, Guess
Page Count
39 pages
Physical Format
Microform
Identifiers
- Open LibraryOL14706451M
Subjects
Topics
TestingPressurized water reactorsEmergency core cooling systemsPressurized water reactors -- Emergency core cooling systems -- Testing
Series Statement
- International agreement report -- NUREG/IA-0052.
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