Show simple item record

contributor authorQian, Guian
contributor authorNiffenegger, Markus
date accessioned2017-05-09T01:23:15Z
date available2017-05-09T01:23:15Z
date issued2015
identifier issn0094-9930
identifier otherpvt_137_06_061206.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/159532
description abstractBoth deterministic and probabilistic methods are used to assess the integrity of a reactor pressure vessel (RPV) subjected to pressurized thermal shocks (PTSs). The FAVOR code is applied to calculate the probabilities for crack initiation and failure of the RPV subjected to two transients, by considering crack distributions based on cracks observed in the Shoreham and pressure vessel research user facility (PVRUF) RPVs. The crack parameters, i.e., crack density, depth, aspect ratio, orientation, and location are assumed as random variables following different distributions. KI of the cracks with the same depth increases with its aspect ratio. Both KI and KIc at the crack tip increase with crack depth, which is the reason why a deeper crack does not necessarily lead to a higher failure probability. The underclad crack is the most critical crack and the deeper crack is the least critical one in this study. Considering uncertainties of the transients results in higher failure probabilities.
publisherThe American Society of Mechanical Engineers (ASME)
titleProbabilistic Pressurized Thermal Shocks Analyses for a Reactor Pressure Vessel
typeJournal Paper
journal volume137
journal issue6
journal titleJournal of Pressure Vessel Technology
identifier doi10.1115/1.4030299
journal fristpage61206
journal lastpage61206
identifier eissn1528-8978
treeJournal of Pressure Vessel Technology:;2015:;volume( 137 ):;issue: 006
contenttypeFulltext


Files in this item

Thumbnail

This item appears in the following Collection(s)

Show simple item record