Extensions of the failure assessment diagram approach semi-elliptical flaw in pressurized cylinder
Journal Article
·
· J. Pressure Vessel Technol.; (United States)
A simple, viable engineering method for assessing the integrity of nuclear pressure vessels has been developed at Babcock and Wilcox. The method uses results given in a plastic fracture handbook developed by General Electric and which are in the format of the Central Electricity Generation Board of the United Kingdom R-6 failure assessment diagram. The method is currently limited to twodimensional/axisymmetric structural models with continuous flaws. Failure assessment of nuclear pressure vessels with assumed continuous flaws result in the calculation of overly conservative safety margins. This paper presents the extension of the existing failure assessment approach to include semi-elliptical flaw models, as well as example problems which demonstrate increased safety margins over the continuous flaw assumptions. In particular, failure assessment diagram curves and the corresponding failure assessment point expressions for an axially cracked pressurized cylinder with an ASME Section III, Appendix G semi-elliptical flaw are presented. The results of the example problems considering the less conservative semi-elliptical flaw model versus the continuous flaw model dramatically illustrate increased safety margins of 50 percent when more realistic semi-elliptical flaws are postulated. The results given in this paper are particularly valuable in the safety assessment of PWR vessels which have low toughness welds in their beltline regions.
- Research Organization:
- Babcock and Wilcox, A McDermott Company, Research and Development Division, Alliance, OH
- OSTI ID:
- 6093655
- Journal Information:
- J. Pressure Vessel Technol.; (United States), Journal Name: J. Pressure Vessel Technol.; (United States) Vol. 107:1; ISSN JPVTA
- Country of Publication:
- United States
- Language:
- English
Similar Records
Extensions of the failure assessment diagram approach: Semi-elliptical flaw in pressurized cylinder
Application of the failure assessment diagram to the evaluation of pressure-temperature limits for a pressurized water reactor
Towards an analysis of leak-before-break assessments in the ductile tearing regime
Conference
·
Mon Oct 31 23:00:00 EST 1983
· Am. Soc. Mech. Eng., (Pap.); (United States)
·
OSTI ID:6714279
Application of the failure assessment diagram to the evaluation of pressure-temperature limits for a pressurized water reactor
Conference
·
Fri Jun 01 00:00:00 EDT 1984
· Am. Soc. Mech. Eng., (Pap.); (United States)
·
OSTI ID:6291248
Towards an analysis of leak-before-break assessments in the ductile tearing regime
Conference
·
Mon Dec 30 23:00:00 EST 1991
·
OSTI ID:10139672
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
CONTAINERS
DEFECTS
FAILURE MODE ANALYSIS
FAILURES
FRACTURE MECHANICS
FRACTURE PROPERTIES
FRACTURES
JOINTS
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
MECHANICS
POWER REACTORS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
CONTAINERS
DEFECTS
FAILURE MODE ANALYSIS
FAILURES
FRACTURE MECHANICS
FRACTURE PROPERTIES
FRACTURES
JOINTS
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
MECHANICS
POWER REACTORS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS