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Probabilistic assessment of creep crack growth rate for Gr. 91 steel
► We use the three methods, a least square fitting method (LSFM), mean value method (MVM) and probabilistic distribution method (PDM), to assess creep crack growth rate (CCGR) for Gr. 91. ► The PDM is found to be the most useful. ► The data of both the B and q coefficients follow lognormal distribut...
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Published in: | Nuclear engineering and design 2011-09, Vol.241 (9), p.3580-3586 |
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creator | Kim, Woo-Gon Park, Jae-Young Hong, Sung-Deok Kim, Seon-Jin |
description | ► We use the three methods, a least square fitting method (LSFM), mean value method (MVM) and probabilistic distribution method (PDM), to assess creep crack growth rate (CCGR) for Gr. 91. ► The PDM is found to be the most useful. ► The data of both the
B and
q coefficients follow lognormal distribution well. A great number of random variables for the
B and
q are generated by Monte Carlo simulation (MCS) technique. ► We predict the probability CCGR lines for 10% and 90% using the MCS results.
This paper focuses on a probabilistic assessment of creep crack growth rate (CCGR) for Gr. 91 steel which is regarded as one of major structural materials of Gen-IV reactors. A series of creep creak growth (CCG) data was obtained from the CCG tests under various applied loads at 600
°C. Using the experimental CCG data, four methods such as a least square fitting method (LSFM), mean value method (MVM), probabilistic distribution method (PDM), and the Monte Carlo method (MCM) were used to determine the parameters
B and
q for a power law equation between CCGR and
C
* integral. The commonly used LSFM revealed a considerable difference in the CCGR lines compared with the MVM and PDM. The PDM was found to be more useful than the LSFM, because it can assess the CCGR lines from the probabilistic viewpoints. It was verified that the two parameters
B and
q followed a lognormal distribution well. From the lognormal distribution, a number of random variables for the
B and
q parameters were successfully generated by the Monte Carlo Simulation (MCS) technique. The CCGR lines for the 10% and 90% probabilities were predicted by the PDM and MCM, and the MCM result was compared with the PDM one. |
doi_str_mv | 10.1016/j.nucengdes.2011.06.042 |
format | article |
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B and
q coefficients follow lognormal distribution well. A great number of random variables for the
B and
q are generated by Monte Carlo simulation (MCS) technique. ► We predict the probability CCGR lines for 10% and 90% using the MCS results.
This paper focuses on a probabilistic assessment of creep crack growth rate (CCGR) for Gr. 91 steel which is regarded as one of major structural materials of Gen-IV reactors. A series of creep creak growth (CCG) data was obtained from the CCG tests under various applied loads at 600
°C. Using the experimental CCG data, four methods such as a least square fitting method (LSFM), mean value method (MVM), probabilistic distribution method (PDM), and the Monte Carlo method (MCM) were used to determine the parameters
B and
q for a power law equation between CCGR and
C
* integral. The commonly used LSFM revealed a considerable difference in the CCGR lines compared with the MVM and PDM. The PDM was found to be more useful than the LSFM, because it can assess the CCGR lines from the probabilistic viewpoints. It was verified that the two parameters
B and
q followed a lognormal distribution well. From the lognormal distribution, a number of random variables for the
B and
q parameters were successfully generated by the Monte Carlo Simulation (MCS) technique. The CCGR lines for the 10% and 90% probabilities were predicted by the PDM and MCM, and the MCM result was compared with the PDM one.</description><identifier>ISSN: 0029-5493</identifier><identifier>EISSN: 1872-759X</identifier><identifier>DOI: 10.1016/j.nucengdes.2011.06.042</identifier><identifier>CODEN: NEDEAU</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Controled nuclear fusion plants ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Fission nuclear power plants ; Fuels ; Installations for energy generation and conversion: thermal and electrical energy ; Nuclear fuels</subject><ispartof>Nuclear engineering and design, 2011-09, Vol.241 (9), p.3580-3586</ispartof><rights>2011</rights><rights>2015 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c377t-85c29d5ad4febec04568c6fd51b8d87ef89fd3fa824972de6fe159eb32966f943</citedby><cites>FETCH-LOGICAL-c377t-85c29d5ad4febec04568c6fd51b8d87ef89fd3fa824972de6fe159eb32966f943</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,780,784,27924,27925</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=24537382$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Kim, Woo-Gon</creatorcontrib><creatorcontrib>Park, Jae-Young</creatorcontrib><creatorcontrib>Hong, Sung-Deok</creatorcontrib><creatorcontrib>Kim, Seon-Jin</creatorcontrib><title>Probabilistic assessment of creep crack growth rate for Gr. 91 steel</title><title>Nuclear engineering and design</title><description>► We use the three methods, a least square fitting method (LSFM), mean value method (MVM) and probabilistic distribution method (PDM), to assess creep crack growth rate (CCGR) for Gr. 91. ► The PDM is found to be the most useful. ► The data of both the
B and
q coefficients follow lognormal distribution well. A great number of random variables for the
B and
q are generated by Monte Carlo simulation (MCS) technique. ► We predict the probability CCGR lines for 10% and 90% using the MCS results.
This paper focuses on a probabilistic assessment of creep crack growth rate (CCGR) for Gr. 91 steel which is regarded as one of major structural materials of Gen-IV reactors. A series of creep creak growth (CCG) data was obtained from the CCG tests under various applied loads at 600
°C. Using the experimental CCG data, four methods such as a least square fitting method (LSFM), mean value method (MVM), probabilistic distribution method (PDM), and the Monte Carlo method (MCM) were used to determine the parameters
B and
q for a power law equation between CCGR and
C
* integral. The commonly used LSFM revealed a considerable difference in the CCGR lines compared with the MVM and PDM. The PDM was found to be more useful than the LSFM, because it can assess the CCGR lines from the probabilistic viewpoints. It was verified that the two parameters
B and
q followed a lognormal distribution well. From the lognormal distribution, a number of random variables for the
B and
q parameters were successfully generated by the Monte Carlo Simulation (MCS) technique. The CCGR lines for the 10% and 90% probabilities were predicted by the PDM and MCM, and the MCM result was compared with the PDM one.</description><subject>Applied sciences</subject><subject>Controled nuclear fusion plants</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fission nuclear power plants</subject><subject>Fuels</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Nuclear fuels</subject><issn>0029-5493</issn><issn>1872-759X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2011</creationdate><recordtype>article</recordtype><recordid>eNqFkE1LxDAQhoMouK7-BnMRT61J2ubjKH6DoAcFbyFNJpq1266ZruK_t8uKV-cwc3neGeYh5JizkjMuzxZlv_bQvwbAUjDOSyZLVosdMuNaiUI15mWXzBgTpmhqU-2TA8QF25QRM3L5mIfWtalLOCZPHSIgLqEf6RCpzwCrqTv_Tl_z8DW-0exGoHHI9CaX1HCKI0B3SPai6xCOfuecPF9fPV3cFvcPN3cX5_eFr5QaC914YULjQh2hBc_qRmovY2h4q4NWELWJoYpOi9ooEUBG4I2BthJGymjqak5Ot3tXefhYA452mdBD17kehjVaI6TQShs-kWpL-jwgZoh2ldPS5W_Lmd1oswv7p81utFkm7aRtSp783nDoXRez633Cv7iom0pVesOdbzmYHv5MkC36BL2HkDL40YYh_XvrB7vTh5M</recordid><startdate>20110901</startdate><enddate>20110901</enddate><creator>Kim, Woo-Gon</creator><creator>Park, Jae-Young</creator><creator>Hong, Sung-Deok</creator><creator>Kim, Seon-Jin</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7SP</scope><scope>7SU</scope><scope>7TB</scope><scope>8FD</scope><scope>C1K</scope><scope>FR3</scope><scope>KR7</scope><scope>L7M</scope></search><sort><creationdate>20110901</creationdate><title>Probabilistic assessment of creep crack growth rate for Gr. 91 steel</title><author>Kim, Woo-Gon ; Park, Jae-Young ; Hong, Sung-Deok ; Kim, Seon-Jin</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c377t-85c29d5ad4febec04568c6fd51b8d87ef89fd3fa824972de6fe159eb32966f943</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2011</creationdate><topic>Applied sciences</topic><topic>Controled nuclear fusion plants</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Fission nuclear power plants</topic><topic>Fuels</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Nuclear fuels</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Kim, Woo-Gon</creatorcontrib><creatorcontrib>Park, Jae-Young</creatorcontrib><creatorcontrib>Hong, Sung-Deok</creatorcontrib><creatorcontrib>Kim, Seon-Jin</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Electronics & Communications Abstracts</collection><collection>Environmental Engineering Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Engineering Research Database</collection><collection>Civil Engineering Abstracts</collection><collection>Advanced Technologies Database with Aerospace</collection><jtitle>Nuclear engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Kim, Woo-Gon</au><au>Park, Jae-Young</au><au>Hong, Sung-Deok</au><au>Kim, Seon-Jin</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Probabilistic assessment of creep crack growth rate for Gr. 91 steel</atitle><jtitle>Nuclear engineering and design</jtitle><date>2011-09-01</date><risdate>2011</risdate><volume>241</volume><issue>9</issue><spage>3580</spage><epage>3586</epage><pages>3580-3586</pages><issn>0029-5493</issn><eissn>1872-759X</eissn><coden>NEDEAU</coden><abstract>► We use the three methods, a least square fitting method (LSFM), mean value method (MVM) and probabilistic distribution method (PDM), to assess creep crack growth rate (CCGR) for Gr. 91. ► The PDM is found to be the most useful. ► The data of both the
B and
q coefficients follow lognormal distribution well. A great number of random variables for the
B and
q are generated by Monte Carlo simulation (MCS) technique. ► We predict the probability CCGR lines for 10% and 90% using the MCS results.
This paper focuses on a probabilistic assessment of creep crack growth rate (CCGR) for Gr. 91 steel which is regarded as one of major structural materials of Gen-IV reactors. A series of creep creak growth (CCG) data was obtained from the CCG tests under various applied loads at 600
°C. Using the experimental CCG data, four methods such as a least square fitting method (LSFM), mean value method (MVM), probabilistic distribution method (PDM), and the Monte Carlo method (MCM) were used to determine the parameters
B and
q for a power law equation between CCGR and
C
* integral. The commonly used LSFM revealed a considerable difference in the CCGR lines compared with the MVM and PDM. The PDM was found to be more useful than the LSFM, because it can assess the CCGR lines from the probabilistic viewpoints. It was verified that the two parameters
B and
q followed a lognormal distribution well. From the lognormal distribution, a number of random variables for the
B and
q parameters were successfully generated by the Monte Carlo Simulation (MCS) technique. The CCGR lines for the 10% and 90% probabilities were predicted by the PDM and MCM, and the MCM result was compared with the PDM one.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.nucengdes.2011.06.042</doi><tpages>7</tpages></addata></record> |
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subjects | Applied sciences Controled nuclear fusion plants Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Fuels Installations for energy generation and conversion: thermal and electrical energy Nuclear fuels |
title | Probabilistic assessment of creep crack growth rate for Gr. 91 steel |
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