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contributor authorT. R. Mager
contributor authorS. E. Yanichko
date accessioned2017-05-09T01:01:06Z
date available2017-05-09T01:01:06Z
date copyrightJune, 1971
date issued1971
identifier issn0098-2202
identifier otherJFEGA4-27379#259_1.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/152578
description abstractThis paper presents the basis for utilizing fracture mechanics technology based upon data obtained from small Charpy V-notch specimens incorporated in reactor vessel surveillance programs. Included is a brief background on linear elastic fracture mechanics and a discussion of reactor surveillance programs in general. Data obtained from published literature are organized and an empirical approach is proposed to utilize the fracture mechanics technique in surveillance programs. A typical problem is included to demonstrate that the approach discussed can be successfully applied to nuclear pressure vessel safety analysis.
publisherThe American Society of Mechanical Engineers (ASME)
titleUse of Fracture Mechanics in Reactor Vessel Surveillance
typeJournal Paper
journal volume93
journal issue2
journal titleJournal of Fluids Engineering
identifier doi10.1115/1.3425222
journal fristpage259
journal lastpage264
identifier eissn1528-901X
keywordsFracture mechanics
keywordsSurveillance
keywordsReactor vessels AND Safety
treeJournal of Fluids Engineering:;1971:;volume( 093 ):;issue: 002
contenttypeFulltext


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