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contributor authorLu, Kai
contributor authorKatsuyama, Jinya
contributor authorLi, Yinsheng
date accessioned2022-02-04T22:58:04Z
date available2022-02-04T22:58:04Z
date copyright4/1/2020 12:00:00 AM
date issued2020
identifier issn0094-9930
identifier otherpvt_142_02_021208.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4275807
description abstractIn Japan, a probabilistic fracture mechanics (PFM) analysis code PASCAL was developed for structural integrity assessment of reactor pressure vessels (RPVs) considering neutron irradiation embrittlement and pressurized thermal shock (PTS) events. By reflecting the latest knowledge and findings, the evaluation functions are continuously improved and have been incorporated into PASCAL4 which is the most recent version of the PASCAL code. In this paper, the improvements made in PASCAL4 are explained in detail, such as the evaluation model of warm prestressing (WPS) effect, evaluation function of confidence levels for PFM analysis results by considering the epistemic and aleatory uncertainties in probabilistic variables, the recent stress intensity factor (KI) solutions, and improved methods for KI calculations when considering complicated stress distributions. Moreover, using PASCAL4, PFM analysis examples considering these improvements are presented.
publisherThe American Society of Mechanical Engineers (ASME)
titleImprovements on Evaluation Functions of a Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessels
typeJournal Paper
journal volume142
journal issue2
journal titleJournal of Pressure Vessel Technology
identifier doi10.1115/1.4045512
journal fristpage021208-1
journal lastpage021208-11
page11
treeJournal of Pressure Vessel Technology:;2020:;volume( 142 ):;issue: 002
contenttypeFulltext


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