Application of the failure assessment diagram to the evaluation of pressure-temperature limits for a pressurized water reactor
Journal Article
·
· J. Pressure Vessel Technol.; (United States)
The failure assessment diagram approach, an elastic-plastic fracture mechanics procedure based on the J-integral concept, was used in the evaluation of pressuretemperature (P-T) limits for the beltline region of the vessel of a pressurized water reactor. The main objective of this paper is to illustrate the application of an alternate fracture mechanics method for the evaluation of pressure-temperature limits, as allowed by the Code of the Federal Regulation 10 CFR 50, Appendix G. The maximum allowable pressure levels were calculated at 33 time points along the given reactor bulk coolant temperature history representing the normal operation of a pressurized water reactor. The results of the calculations showed that adequate margins of safety on operating pressure for the critical weld in the beltline of the pressurized water reactor vessel are assured.
- Research Organization:
- The Babcock and Wilcox Company, Nuclear Power Division, Lynchburg, VA
- OSTI ID:
- 6310378
- Journal Information:
- J. Pressure Vessel Technol.; (United States), Journal Name: J. Pressure Vessel Technol.; (United States) Vol. 107:2; ISSN JPVTA
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BUILDING CODES
CONTAINERS
FAILURE MODE ANALYSIS
FRACTURE MECHANICS
JOINTS
LIMITING VALUES
MECHANICS
NATIONAL ORGANIZATIONS
PRESSURE EFFECTS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTORS
REGULATIONS
SAFEGUARD REGULATIONS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TEMPERATURE EFFECTS
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BUILDING CODES
CONTAINERS
FAILURE MODE ANALYSIS
FRACTURE MECHANICS
JOINTS
LIMITING VALUES
MECHANICS
NATIONAL ORGANIZATIONS
PRESSURE EFFECTS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTORS
REGULATIONS
SAFEGUARD REGULATIONS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TEMPERATURE EFFECTS
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS