Application of leak-before-break justification approach to BWR piping
Conference
·
· Proceedings of the American Power Conference; (USA)
OSTI ID:7038477
- Electric Power Research Inst., Palo Alto, CA (USA)
The NRC has published initial guidelines for application of the leak-before-break (LBB) approach. This paper reports the results of a study to develop criteria for applying the LBB approach to boiling water reactor (BWR) piping systems and to determine the order in which high energy piping systems should receive LBB evaluations. The author identify major LBB related to the fracture mechanics technology in the application of the LBB approach. They demonstrate a typical LBB analysis.
- OSTI ID:
- 7038477
- Report Number(s):
- CONF-880403--
- Conference Information:
- Journal Name: Proceedings of the American Power Conference; (USA) Journal Volume: 50
- Country of Publication:
- United States
- Language:
- English
Similar Records
Application of the leak-before-break approach to BWR piping: Final report
Application of leak-before-break approach to PWR piping designed by Babcock and Wilcox: Final report
Application of leak-before-break analysis to PWR (pressurized water reactor) piping designed by Combustion Engineering: Final report
Technical Report
·
Sun Nov 30 23:00:00 EST 1986
·
OSTI ID:7124607
Application of leak-before-break approach to PWR piping designed by Babcock and Wilcox: Final report
Technical Report
·
Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:7144260
Application of leak-before-break analysis to PWR (pressurized water reactor) piping designed by Combustion Engineering: Final report
Technical Report
·
Sat Jan 31 23:00:00 EST 1987
·
OSTI ID:6660529
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220400* -- Nuclear Reactor Technology-- Control Systems
220900 -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
FRACTURE MECHANICS
LEAK DETECTORS
LOSS OF COOLANT
MECHANICS
NATIONAL ORGANIZATIONS
PIPES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR MONITORING SYSTEMS
REACTORS
RECOMMENDATIONS
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220400* -- Nuclear Reactor Technology-- Control Systems
220900 -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
FRACTURE MECHANICS
LEAK DETECTORS
LOSS OF COOLANT
MECHANICS
NATIONAL ORGANIZATIONS
PIPES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR MONITORING SYSTEMS
REACTORS
RECOMMENDATIONS
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS