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dc.contributor.authorW. A. Pavinich
dc.contributor.authorW. L. Server
dc.contributor.authorT. J. Griesbach
dc.date.accessioned2017-05-08T23:40:15Z
dc.date.available2017-05-08T23:40:15Z
dc.date.copyrightMay, 1993
dc.date.issued1993
dc.identifier.issn0003-6900
dc.identifier.otherAMREAD-25642#162_1.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl/handle/yetl/111275
dc.description.abstractThe mechanistic models of radiation embrittlement for reactor vessel steels are reviewed and direction for improving these models is provided. Improvement in these mechanistic models will lead to predictive expressions for parameters of engineering interest. This paper provides the initial direction of modelling efforts that will improve existing or develop new predictive equations for damage attenuation, temperature effects, thermal annealing, the effect of post weld heat treatment, transition behavior and upper shelf behavior of reactor vessel steels.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleRadiation Embrittlement Mechanistic Modelling
dc.typeJournal Paper
dc.journal.volume46
dc.journal.issue5
dc.journal.titleApplied Mechanics Reviews
dc.identifier.doi10.1115/1.3120326
dc.journal.fristpage162
dc.journal.lastpage170
dc.identifier.eissn0003-6900
dc.keywordsRadiation (Physics)
dc.keywordsModeling
dc.keywordsEmbrittlement
dc.keywordsSteel
dc.keywordsReactor vessels
dc.keywordsEquations
dc.keywordsAnnealing
dc.keywordsHeat treating (Metalworking) AND Temperature effects
dc.treeApplied Mechanics Reviews:;1993:;volume( 046 ):;issue: 005
dc.contenttypeFulltext


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