BWR reactor water cleanup system flexible wedge gate isolation value qualification and high energy flow interruption test
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Author
Contributions
- Steele, Robert. - Contributor
- U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering. - Contributor
- U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution. - Contributor
- Idaho National Engineering Laboratory. - Contributor
Publication
1989 - Division of Engineering, Washington, DC, District of Columbia
Language
English
Subjects
Topics
ValvesPipingTestingSafety measuresValves -- TestingNuclear power plantsBoiling water reactorsBoiling water reactors -- Safety measuresNuclear power plants -- Piping -- Valves -- Testing
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