CSNI specialist meeting on leak-before-break in nuclear reactor piping: proceedings

Conference · Wed Aug 01 00:00:00 EDT 1984

OSTI ID:6257699

On September 1 and 2, 1983, the CSNI subcommittee on primary system integrity held a special meeting in Monterey, California, on the subject of leak-before-break in nuclear reactor piping systems. The purpose of the meeting was to provide an international forum for the exchange of ideas, positions, and research results; to identify areas requiring additional research and development; and to determine the general attitude toward acceptance of the leak-before-break concept. The importance of the leak-before-break issue was evidenced by excellent attendance at the meeting and through active participation by the meeting attendees. Approximately 125 people representing fifteen different nations attended the meeting. The meeting was divided into four technical sessions addressing the following areas: Application of Piping Fracture Mechanics to Leak-Before Break, Leak Rate and Leak Detection, Leak-Before-Break Studies, Methods and Results, Current and Proposed Positions on Leak-Before-Break.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research
• OSTI ID: 6257699
• Report Number(s): NUREG/CP-0051; CONF-8309187-; ON: TI84901888
• Resource Relation: Conference: CSNI leak-before-break conference, Monterey, CA, USA, 1 Sep 1983; Other Information: CSNI Report No. 82
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
PRIMARY COOLANT CIRCUITS
LEAK TESTING
MEETINGS
NUCLEAR POWER PLANTS
CRACK PROPAGATION
LOSS OF COOLANT
PWR TYPE REACTORS
CRACKS
FLOW MODELS
GRAPHS
LEADING ABSTRACT
LEAK DETECTORS
LEAKS
MATHEMATICAL MODELS
MEASURING METHODS
PIPES
REACTOR SAFETY
STAINLESS STEEL-304
TABLES
ABSTRACTS
ACCIDENTS
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COOLING SYSTEMS
CORROSION RESISTANT ALLOYS
DOCUMENT TYPES
ENERGY SYSTEMS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
NICKEL ALLOYS
NUCLEAR FACILITIES
POWER PLANTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
STAINLESS STEELS
STEELS
TESTING
THERMAL POWER PLANTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
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Light-Water Moderated
Nonboiling Water Cooled