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contributor authorKatsuyama, Jinya
contributor authorOsakabe, Kazuya
contributor authorUno, Shumpei
contributor authorLi, Yinsheng
contributor authorYoshimura, Shinobu
date accessioned2022-02-04T14:27:44Z
date available2022-02-04T14:27:44Z
date copyright2020/02/24/
date issued2020
identifier issn0094-9930
identifier otherpvt_142_02_021205.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4273701
description abstractIn Japan, to prevent nil-ductile fracture of reactor pressure vessels (RPVs) due to neutron irradiation embrittlement, deterministic fracture mechanics evaluation in accordance with the codes provided by the Japan Electric Association is performed for assessing the structural integrity of RPVs under pressurized thermal shock (PTS) events considering neutron irradiation embrittlement. In recent years, a structural integrity assessment methodology based on probabilistic fracture mechanics (PFM) has been introduced into the regulations in the United States and a few European countries. PFM is a rational methodology for evaluating the failure frequency of important pressure boundary components by considering the probabilistic distributions of various influence factors related to aged degradation due to the long-term operation. In Japan Atomic Energy Agency (JAEA), a PFM analysis code called PASCAL has been developed to evaluate the failure frequency of RPVs considering neutron irradiation embrittlement and PTS events. In addition, we have developed a guideline for structural integrity assessment of RPVs based on PFM to improve the applicability of PFM in Japan and enable persons who have knowledge on fracture mechanics to perform PFM analyses and evaluate through-wall cracking frequency (TWCF) of RPVs easily. The guideline consists of a main body, explanation, and several supplements. The technical basis for PFM analysis is provided, and the latest knowledge is included in the guideline. In this paper, an overview of the guideline and some typical analysis results obtained based on the guideline and the Japanese database related to PTS evaluation are presented.
publisherThe American Society of Mechanical Engineers (ASME)
titleGuideline on Probabilistic Fracture Mechanics Analysis for Japanese Reactor Pressure Vessels
typeJournal Paper
journal volume142
journal issue2
journal titleJournal of Pressure Vessel Technology
identifier doi10.1115/1.4045874
page21205
treeJournal of Pressure Vessel Technology:;2020:;volume( 142 ):;issue: 002
contenttypeFulltext


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