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contributor authorFredric A. Simonen
contributor authorStephen R. Gosselin
date accessioned2017-05-09T00:05:50Z
date available2017-05-09T00:05:50Z
date copyrightFebruary, 2001
date issued2001
identifier issn0094-9930
identifier otherJPVTAS-28407#58_1.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/125772
description abstractThis paper describes industry programs to manage structural degradation and to justify continued operation of nuclear components when unexpected degradation has been encountered due to design materials and/or operational problems. Other issues have been related to operation of components beyond their original design life in cases where there is no evidence of fatigue crack initiation or other forms of structural degradation. Data from plant operating experience have been applied in combination with inservice inspections and degradation management programs to ensure that the degradation mechanisms do not adversely impact plant safety. Probabilistic fracture mechanics calculations are presented to demonstrate how component failure probabilities can be managed through augmented inservice inspection programs.
publisherThe American Society of Mechanical Engineers (ASME)
titleLife Prediction and Monitoring of Nuclear Power Plant Components for Service-Related Degradation
typeJournal Paper
journal volume123
journal issue1
journal titleJournal of Pressure Vessel Technology
identifier doi10.1115/1.1344237
journal fristpage58
journal lastpage64
identifier eissn1528-8978
keywordsDesign
keywordsPipes
keywordsSurgery
keywordsFailure
keywordsIndustrial plants
keywordsNuclear power stations
keywordsProbability
keywordsFatigue
keywordsInspection
keywordsLeakage AND Corrosion
treeJournal of Pressure Vessel Technology:;2001:;volume( 123 ):;issue: 001
contenttypeFulltext


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