Development of probabilistic fracture mechanics analysis codes for reactor pressure vessels and piping considering welding residual stress
Probabilistic fracture mechanics (PFM) analysis codes for reactor pressure vessels (RPVs) and piping, called as PASCAL (PFM Analysis of Structural Components in Aging LWRs) series, have been developed. The PASCAL2 (PASCAL version 2) evaluates the conditional probability of fracture of an RPV under t...
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Veröffentlicht in: | International journal of pressure vessels and piping 2010, Vol.87 (1), p.2-10 |
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creator | Onizawa, Kunio Nishikawa, Hiroyuki Itoh, Hiroto |
description | Probabilistic fracture mechanics (PFM) analysis codes for reactor pressure vessels (RPVs) and piping, called as PASCAL (PFM Analysis of Structural Components in Aging LWRs) series, have been developed. The PASCAL2 (PASCAL version 2) evaluates the conditional probability of fracture of an RPV under transient conditions including pressurized thermal shock (PTS) considering neutron irradiation embrittlement of the vessels. Recent improvements to PASCAL2 are related to the treatment of weld–overlay cladding. The results using the improved code indicate that the residual stress by weld–overlay cladding affects the fracture probability to some extent. The PASCAL-SP (PASCAL – Stress corrosion cracking at welding joints for Piping) evaluates the probabilities of failures including leakage and breaks of safety-related piping complying with Japanese regulation and rules. Effects of welding residual stress distribution as well as inspection accuracy are focused in this study. Residual stress distributions have been determined by parametric FEM analyses and incorporated into the code. |
doi_str_mv | 10.1016/j.ijpvp.2009.11.011 |
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The PASCAL2 (PASCAL version 2) evaluates the conditional probability of fracture of an RPV under transient conditions including pressurized thermal shock (PTS) considering neutron irradiation embrittlement of the vessels. Recent improvements to PASCAL2 are related to the treatment of weld–overlay cladding. The results using the improved code indicate that the residual stress by weld–overlay cladding affects the fracture probability to some extent. The PASCAL-SP (PASCAL – Stress corrosion cracking at welding joints for Piping) evaluates the probabilities of failures including leakage and breaks of safety-related piping complying with Japanese regulation and rules. Effects of welding residual stress distribution as well as inspection accuracy are focused in this study. Residual stress distributions have been determined by parametric FEM analyses and incorporated into the code.</description><identifier>ISSN: 0308-0161</identifier><identifier>EISSN: 1879-3541</identifier><identifier>DOI: 10.1016/j.ijpvp.2009.11.011</identifier><identifier>CODEN: PRVPAS</identifier><language>eng</language><publisher>Kidlington: Elsevier Ltd</publisher><subject>Applied sciences ; Cladding ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Finite element method ; Fission nuclear power plants ; Fracture mechanics ; Fracture mechanics (crack, fatigue, damage...) ; Fundamental areas of phenomenology (including applications) ; Installations for energy generation and conversion: thermal and electrical energy ; Mechanical engineering. Machine design ; Pascal (programming language) ; Physics ; Piping ; Pressure vessels ; Probabilistic fracture mechanics ; Reactor pressure vessel ; Residual stress ; Solid mechanics ; Static elasticity (thermoelasticity...) ; Steel design ; Steel tanks and pressure vessels; boiler manufacturing ; Stress corrosion cracking ; Structural and continuum mechanics ; Welding ; Welding residual stress</subject><ispartof>International journal of pressure vessels and piping, 2010, Vol.87 (1), p.2-10</ispartof><rights>2009 Elsevier Ltd</rights><rights>2015 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c432t-48c13093fa1eed63331d71aa11e8a14b1a22df366b84fa8602423b0bd2263d343</citedby><cites>FETCH-LOGICAL-c432t-48c13093fa1eed63331d71aa11e8a14b1a22df366b84fa8602423b0bd2263d343</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S030801610900177X$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>309,310,314,776,780,785,786,3537,4010,4036,4037,23909,23910,25118,27900,27901,27902,65306</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=22465773$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Onizawa, Kunio</creatorcontrib><creatorcontrib>Nishikawa, Hiroyuki</creatorcontrib><creatorcontrib>Itoh, Hiroto</creatorcontrib><title>Development of probabilistic fracture mechanics analysis codes for reactor pressure vessels and piping considering welding residual stress</title><title>International journal of pressure vessels and piping</title><description>Probabilistic fracture mechanics (PFM) analysis codes for reactor pressure vessels (RPVs) and piping, called as PASCAL (PFM Analysis of Structural Components in Aging LWRs) series, have been developed. The PASCAL2 (PASCAL version 2) evaluates the conditional probability of fracture of an RPV under transient conditions including pressurized thermal shock (PTS) considering neutron irradiation embrittlement of the vessels. Recent improvements to PASCAL2 are related to the treatment of weld–overlay cladding. The results using the improved code indicate that the residual stress by weld–overlay cladding affects the fracture probability to some extent. The PASCAL-SP (PASCAL – Stress corrosion cracking at welding joints for Piping) evaluates the probabilities of failures including leakage and breaks of safety-related piping complying with Japanese regulation and rules. Effects of welding residual stress distribution as well as inspection accuracy are focused in this study. Residual stress distributions have been determined by parametric FEM analyses and incorporated into the code.</description><subject>Applied sciences</subject><subject>Cladding</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Finite element method</subject><subject>Fission nuclear power plants</subject><subject>Fracture mechanics</subject><subject>Fracture mechanics (crack, fatigue, damage...)</subject><subject>Fundamental areas of phenomenology (including applications)</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Mechanical engineering. Machine design</subject><subject>Pascal (programming language)</subject><subject>Physics</subject><subject>Piping</subject><subject>Pressure vessels</subject><subject>Probabilistic fracture mechanics</subject><subject>Reactor pressure vessel</subject><subject>Residual stress</subject><subject>Solid mechanics</subject><subject>Static elasticity (thermoelasticity...)</subject><subject>Steel design</subject><subject>Steel tanks and pressure vessels; boiler manufacturing</subject><subject>Stress corrosion cracking</subject><subject>Structural and continuum mechanics</subject><subject>Welding</subject><subject>Welding residual stress</subject><issn>0308-0161</issn><issn>1879-3541</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2010</creationdate><recordtype>article</recordtype><recordid>eNp9kMFu1DAQhi0EEkvLE3DxBYlLUo-ddbIHDqi0gFSJSzlbjj2BWXmT4Mku6ivw1HXYimNP_xy-f0bzCfEOVA0K7NW-pv18mmut1K4GqBXAC7GBrt1VZtvAS7FRRnVVQeG1eMO8VwpatbUb8fcznjBN8wHHRU6DnPPU-54S8UJBDtmH5ZhRHjD88iMFln706YGJZZgishymLDMWquSckXmlTyUxrWyUM800_iz0yBQxr_MfTHHNglM8-iR5WZuX4tXgE-Pbp7wQP25v7q-_Vnffv3y7_nRXhcbopWq6AEbtzOABMVpjDMQWvAfAzkPTg9c6DsbavmsG31mlG2161UetrYmmMRfiw3lv-fX3EXlxB-KAKfkRpyM7sC1oo1qtCmrOaMgTc8bBzZkOPj84UG417_bun3m3mncArpgvrfdPBzwHn4rEMRD_r2rd2G3bmsJ9PHPFFZ4Is-NAOAaMlDEsLk707J1HZwmeFA</recordid><startdate>2010</startdate><enddate>2010</enddate><creator>Onizawa, Kunio</creator><creator>Nishikawa, Hiroyuki</creator><creator>Itoh, Hiroto</creator><general>Elsevier Ltd</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7TB</scope><scope>8FD</scope><scope>FR3</scope><scope>KR7</scope></search><sort><creationdate>2010</creationdate><title>Development of probabilistic fracture mechanics analysis codes for reactor pressure vessels and piping considering welding residual stress</title><author>Onizawa, Kunio ; Nishikawa, Hiroyuki ; Itoh, Hiroto</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c432t-48c13093fa1eed63331d71aa11e8a14b1a22df366b84fa8602423b0bd2263d343</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2010</creationdate><topic>Applied sciences</topic><topic>Cladding</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Finite element method</topic><topic>Fission nuclear power plants</topic><topic>Fracture mechanics</topic><topic>Fracture mechanics (crack, fatigue, damage...)</topic><topic>Fundamental areas of phenomenology (including applications)</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Mechanical engineering. Machine design</topic><topic>Pascal (programming language)</topic><topic>Physics</topic><topic>Piping</topic><topic>Pressure vessels</topic><topic>Probabilistic fracture mechanics</topic><topic>Reactor pressure vessel</topic><topic>Residual stress</topic><topic>Solid mechanics</topic><topic>Static elasticity (thermoelasticity...)</topic><topic>Steel design</topic><topic>Steel tanks and pressure vessels; boiler manufacturing</topic><topic>Stress corrosion cracking</topic><topic>Structural and continuum mechanics</topic><topic>Welding</topic><topic>Welding residual stress</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Onizawa, Kunio</creatorcontrib><creatorcontrib>Nishikawa, Hiroyuki</creatorcontrib><creatorcontrib>Itoh, Hiroto</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Civil Engineering Abstracts</collection><jtitle>International journal of pressure vessels and piping</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Onizawa, Kunio</au><au>Nishikawa, Hiroyuki</au><au>Itoh, Hiroto</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Development of probabilistic fracture mechanics analysis codes for reactor pressure vessels and piping considering welding residual stress</atitle><jtitle>International journal of pressure vessels and piping</jtitle><date>2010</date><risdate>2010</risdate><volume>87</volume><issue>1</issue><spage>2</spage><epage>10</epage><pages>2-10</pages><issn>0308-0161</issn><eissn>1879-3541</eissn><coden>PRVPAS</coden><abstract>Probabilistic fracture mechanics (PFM) analysis codes for reactor pressure vessels (RPVs) and piping, called as PASCAL (PFM Analysis of Structural Components in Aging LWRs) series, have been developed. The PASCAL2 (PASCAL version 2) evaluates the conditional probability of fracture of an RPV under transient conditions including pressurized thermal shock (PTS) considering neutron irradiation embrittlement of the vessels. Recent improvements to PASCAL2 are related to the treatment of weld–overlay cladding. The results using the improved code indicate that the residual stress by weld–overlay cladding affects the fracture probability to some extent. The PASCAL-SP (PASCAL – Stress corrosion cracking at welding joints for Piping) evaluates the probabilities of failures including leakage and breaks of safety-related piping complying with Japanese regulation and rules. Effects of welding residual stress distribution as well as inspection accuracy are focused in this study. 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subjects | Applied sciences Cladding Energy Energy. Thermal use of fuels Exact sciences and technology Finite element method Fission nuclear power plants Fracture mechanics Fracture mechanics (crack, fatigue, damage...) Fundamental areas of phenomenology (including applications) Installations for energy generation and conversion: thermal and electrical energy Mechanical engineering. Machine design Pascal (programming language) Physics Piping Pressure vessels Probabilistic fracture mechanics Reactor pressure vessel Residual stress Solid mechanics Static elasticity (thermoelasticity...) Steel design Steel tanks and pressure vessels boiler manufacturing Stress corrosion cracking Structural and continuum mechanics Welding Welding residual stress |
title | Development of probabilistic fracture mechanics analysis codes for reactor pressure vessels and piping considering welding residual stress |
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