共 28 条
[1]
ASME Boiler and Pressure Vessel Code, Section XI: Rules for in-service inspection of nuclear power plant components, (1989)
[2]
Marshall, An assessment of the integrity of PWR pressure vessels, (1976)
[3]
Simonen, Johnson, Liebetrau, Engel, Simonen, VISA II—A computer code for predicting the probability of reactor pressure vessel failure, NUREG/CR-4486, PNL-5775, (1986)
[4]
Milne, Ainsworth, Dowling, Stewart, Assessment of the integrity of structures containing defects, CEGB Rep. R/H/R6-Rev. 3, (1988)
[5]
Bergman, Brickstad, Dahlberg, Sattari-Far, Nilsson, A procedure for safety assessment of components with cracks, SA/FoU Rep. 91/01, (1991)
[6]
Nilsson, Faleskog, Zaremba, Oberg, Elastic-plastic fracture mechanics for pressure vessel design, Fatigue and Fract. of Eng. Materials & Structures, 15, pp. 73-89, (1992)
[7]
Ostensson, Experimentell undersökning av brottsegheten hos tryckkärlsstål A-533 B i temperaturintervallet 20°C–350°C, Rep. S-509, (1975)
[8]
Nilsson, Reliability assessment by aid of probabilistic fracture mechanics, OECD/NEA/CSNI Workshop on Safety Assessment of Reactor Pressure Vessels, (1990)
[9]
Raju, Newman, Stress-intensity factor equations for cracks in three-dimensional finite bodies subjected to tension and bending loads, NASA Technical Memorandum 85739, (1984)
[10]
Raju, Newman, Stress-intensity factors for internal and external surface cracks in cylindrical vessels, J. Pres. Ves. Technol., Trans. ASME, 104, pp. 293-298, (1982)

