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AbstractAbstract
[en] A summary of results illustrating what might be derived from a probabilistic risk assessment (PRA) study follows. The failure probabilities for larger sizes of nuclear piping are considered to be in the range of 10-4 to 10-6 per reactor-year (exclusive of intergranular stress corrosion cracking (IGSCC). Smaller pipe sizes, of lesser safety significance, have much higher failure rates. In BWRs, IGSCC can cause failure rates much higher than 10-4 in piping 4 to 10 in. in size. Suggested failure mechanisms apply in most instances, exclusive of IGSCC. Catastrophic failures would appear more likely from operator error or design and construction errors (water hammer, improper handling of dynamic loads, and undetected fabrication defects) rather than conventional flaw initiation and growth by fatigue
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Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research; p. 529-556; Aug 1984; p. 529-556; CSNI leak-before-break conference; Monterey, CA (USA); 1-2 Sep 1983; Available from NTIS, PC A24/MF A01 - GPO* $10.00 as TI84901888
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Report
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Conference
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