$Recent verification activities on probabilistic fracture mechanics analysis code PASCAL4 for reactor pressure vessel$
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Recent verification activities on probabilistic fracture mechanics analysis code PASCAL4 for reactor pressure vessel

Probabilistic fracture mechanics (PFM) is considered a promising methodology in assessing the integrity of structural components in nuclear power plants because it can rationally represent the influence parameters in their probabilistic distributions without over-conservativeness. In Japan, Japan At...

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Autores principales:	Kai LU, Jinya KATSUYAMA, Yinsheng LI, Yuhei MIYAMOTO, Takatoshi HIROTA, Yu ITABASHI, Masaki NAGAI, Masahide SUZUKI, Yasuhiro KANTO
Formato:	article
Lenguaje:	EN
Publicado:	The Japan Society of Mechanical Engineers 2020
Materias:	structural integrity assessment probabilistic fracture mechanics reactor pressure vessel neutron irradiation embrittlement pressurized thermal shock Mechanical engineering and machinery TJ1-1570
Acceso en línea:	https://doaj.org/article/a0cb1ac09d11407d8a3bd69bd0f2080e
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spelling	oai:doaj.org-article:a0cb1ac09d11407d8a3bd69bd0f2080e2021-11-29T05:56:31ZRecent verification activities on probabilistic fracture mechanics analysis code PASCAL4 for reactor pressure vessel2187-974510.1299/mej.19-00573https://doaj.org/article/a0cb1ac09d11407d8a3bd69bd0f2080e2020-01-01T00:00:00Zhttps://www.jstage.jst.go.jp/article/mej/7/3/7_19-00573/_pdf/-char/enhttps://doaj.org/toc/2187-9745Probabilistic fracture mechanics (PFM) is considered a promising methodology in assessing the integrity of structural components in nuclear power plants because it can rationally represent the influence parameters in their probabilistic distributions without over-conservativeness. In Japan, Japan Atomic Energy Agency has developed a PFM analysis code PASCAL4 (PFM Analysis of Structural Components in Aging LWRs Version 4) which enables the probabilistic integrity assessment of reactor pressure vessels (RPVs) considering neutron irradiation embrittlement and pressurized thermal shock events. Several efforts have been made to verify PASCAL4 to ensure that this code can provide reliable analysis results. In particular, a Japanese working group, which consists of different participants from the industry and from universities and institutes, has been established to conduct the verification studies. This paper summarizes verification activities of the working group in the past two years. Based on those verification activities, the reliability and applicability of PASCAL4 for structural integrity assessments of Japanese RPVs have been confirmed with great confidence.Kai LUJinya KATSUYAMAYinsheng LIYuhei MIYAMOTOTakatoshi HIROTAYu ITABASHIMasaki NAGAIMasahide SUZUKIYasuhiro KANTOThe Japan Society of Mechanical Engineersarticlestructural integrity assessmentprobabilistic fracture mechanicsreactor pressure vesselneutron irradiation embrittlementpressurized thermal shockMechanical engineering and machineryTJ1-1570ENMechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00573-19-00573 (2020)
institution	DOAJ
collection	DOAJ
language	EN
topic	structural integrity assessment probabilistic fracture mechanics reactor pressure vessel neutron irradiation embrittlement pressurized thermal shock Mechanical engineering and machinery TJ1-1570
spellingShingle	structural integrity assessment probabilistic fracture mechanics reactor pressure vessel neutron irradiation embrittlement pressurized thermal shock Mechanical engineering and machinery TJ1-1570 Kai LU Jinya KATSUYAMA Yinsheng LI Yuhei MIYAMOTO Takatoshi HIROTA Yu ITABASHI Masaki NAGAI Masahide SUZUKI Yasuhiro KANTO Recent verification activities on probabilistic fracture mechanics analysis code PASCAL4 for reactor pressure vessel
description	Probabilistic fracture mechanics (PFM) is considered a promising methodology in assessing the integrity of structural components in nuclear power plants because it can rationally represent the influence parameters in their probabilistic distributions without over-conservativeness. In Japan, Japan Atomic Energy Agency has developed a PFM analysis code PASCAL4 (PFM Analysis of Structural Components in Aging LWRs Version 4) which enables the probabilistic integrity assessment of reactor pressure vessels (RPVs) considering neutron irradiation embrittlement and pressurized thermal shock events. Several efforts have been made to verify PASCAL4 to ensure that this code can provide reliable analysis results. In particular, a Japanese working group, which consists of different participants from the industry and from universities and institutes, has been established to conduct the verification studies. This paper summarizes verification activities of the working group in the past two years. Based on those verification activities, the reliability and applicability of PASCAL4 for structural integrity assessments of Japanese RPVs have been confirmed with great confidence.
format	article
author	Kai LU Jinya KATSUYAMA Yinsheng LI Yuhei MIYAMOTO Takatoshi HIROTA Yu ITABASHI Masaki NAGAI Masahide SUZUKI Yasuhiro KANTO
author_facet	Kai LU Jinya KATSUYAMA Yinsheng LI Yuhei MIYAMOTO Takatoshi HIROTA Yu ITABASHI Masaki NAGAI Masahide SUZUKI Yasuhiro KANTO
author_sort	Kai LU
title	Recent verification activities on probabilistic fracture mechanics analysis code PASCAL4 for reactor pressure vessel
title_short	Recent verification activities on probabilistic fracture mechanics analysis code PASCAL4 for reactor pressure vessel
title_full	Recent verification activities on probabilistic fracture mechanics analysis code PASCAL4 for reactor pressure vessel
title_fullStr	Recent verification activities on probabilistic fracture mechanics analysis code PASCAL4 for reactor pressure vessel
title_full_unstemmed	Recent verification activities on probabilistic fracture mechanics analysis code PASCAL4 for reactor pressure vessel
title_sort	recent verification activities on probabilistic fracture mechanics analysis code pascal4 for reactor pressure vessel
publisher	The Japan Society of Mechanical Engineers
publishDate	2020
url	https://doaj.org/article/a0cb1ac09d11407d8a3bd69bd0f2080e
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Recent verification activities on probabilistic fracture mechanics analysis code PASCAL4 for reactor pressure vessel

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