Irradiation creep and IASCC prediction method of PWR's core internal: Verification of "Inspection and Evaluation Guideline for Reactor Internals of PWR(Baffle Former Bolt)"
PWR's core internals have aging due to IASCC (Irradiation Assisted Stress Corrosion Cracking). Although stress influences the occurrence of IASCC greatly, we have little data about PWR's irradiation creep which reduces stress. In this report, we assessed irradiation creep by using the remo...
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Veröffentlicht in: | QUARTERLY JOURNAL OF THE JAPAN WELDING SOCIETY 2005, Vol.23(1), pp.77-81 |
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creator | KAMEYAMA, Masashi CHIGUSA, Naoki KUBO, Noboru KATAYAMA, Masaaki |
description | PWR's core internals have aging due to IASCC (Irradiation Assisted Stress Corrosion Cracking). Although stress influences the occurrence of IASCC greatly, we have little data about PWR's irradiation creep which reduces stress. In this report, we assessed irradiation creep by using the removal torque of the baffle former bolts at the time of replacement. Then, we concluded that irradiation creep in PWR is approximately 50% of the irradiation creep in the fast breeder reactor. Moreover, we used this result to check the method for IASCC prediction method proposed in the last report which is applicable also to barrel former bolt and weld metal of barrel, and we confirmed the applicability of the IASCC prediction method for the actual plant. |
doi_str_mv | 10.2207/qjjws.23.77 |
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Although stress influences the occurrence of IASCC greatly, we have little data about PWR's irradiation creep which reduces stress. In this report, we assessed irradiation creep by using the removal torque of the baffle former bolts at the time of replacement. Then, we concluded that irradiation creep in PWR is approximately 50% of the irradiation creep in the fast breeder reactor. Moreover, we used this result to check the method for IASCC prediction method proposed in the last report which is applicable also to barrel former bolt and weld metal of barrel, and we confirmed the applicability of the IASCC prediction method for the actual plant.</description><identifier>ISSN: 0288-4771</identifier><identifier>EISSN: 2434-8252</identifier><identifier>DOI: 10.2207/qjjws.23.77</identifier><language>jpn</language><publisher>JAPAN WELDING SOCIETY</publisher><subject>Baffle former bolt ; Barrel former bolt ; Core internal ; IASCC ; Irradiation creep ; Weld metal of barrel</subject><ispartof>QUARTERLY JOURNAL OF THE JAPAN WELDING SOCIETY, 2005, Vol.23(1), pp.77-81</ispartof><rights>2005 by JAPAN WELDING SOCIETY</rights><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><cites>FETCH-LOGICAL-c2317-de25a163f9bed76cde6bf0dea9c08dadd5d43c79ada6a3a1a204ff4e99be74ee3</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,780,784,1883,27924,27925</link.rule.ids></links><search><creatorcontrib>KAMEYAMA, Masashi</creatorcontrib><creatorcontrib>CHIGUSA, Naoki</creatorcontrib><creatorcontrib>KUBO, Noboru</creatorcontrib><creatorcontrib>KATAYAMA, Masaaki</creatorcontrib><title>Irradiation creep and IASCC prediction method of PWR's core internal: Verification of "Inspection and Evaluation Guideline for Reactor Internals of PWR(Baffle Former Bolt)"</title><title>QUARTERLY JOURNAL OF THE JAPAN WELDING SOCIETY</title><description>PWR's core internals have aging due to IASCC (Irradiation Assisted Stress Corrosion Cracking). Although stress influences the occurrence of IASCC greatly, we have little data about PWR's irradiation creep which reduces stress. In this report, we assessed irradiation creep by using the removal torque of the baffle former bolts at the time of replacement. Then, we concluded that irradiation creep in PWR is approximately 50% of the irradiation creep in the fast breeder reactor. Moreover, we used this result to check the method for IASCC prediction method proposed in the last report which is applicable also to barrel former bolt and weld metal of barrel, and we confirmed the applicability of the IASCC prediction method for the actual plant.</description><subject>Baffle former bolt</subject><subject>Barrel former bolt</subject><subject>Core internal</subject><subject>IASCC</subject><subject>Irradiation creep</subject><subject>Weld metal of barrel</subject><issn>0288-4771</issn><issn>2434-8252</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2005</creationdate><recordtype>article</recordtype><recordid>eNpF0EtLw0AUBeBBFCy1K_9AVrqQ1Hklk-ws8VUoKD5wOdzO3NgpaZLOpIj_3thI3dy7OB9ncQg5Z3TKOVXX2_X6K0y5mCp1REZcChlnPOHHZER5lsVSKXZKJiG4JaVJTlmmshG5nXsP1kHnmjoyHrGNoLbRfPZaFFHr0TqzjzbYrRobNWX0_PFyGSLTeIxc3aGvoTojJyVUASd_f0ze7-_eisd48fQwL2aL2HDBVGyRJ8BSUeZLtCo1FtNlSS1CbmhmwdrESmFUDhZSEMCAU1mWEvPeK4koxuRi6G19s91h6PTGBYNVBTU2u6B5lsq-n_XwaoDGNyF4LHXr3Qb8t2ZU_46l92NpLrRSvb4Z9Dp08IkHC75zpsJ_y4aj1CEyK_Aaa_EDSE92Qg</recordid><startdate>200502</startdate><enddate>200502</enddate><creator>KAMEYAMA, Masashi</creator><creator>CHIGUSA, Naoki</creator><creator>KUBO, Noboru</creator><creator>KATAYAMA, Masaaki</creator><general>JAPAN WELDING SOCIETY</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7SE</scope><scope>7TB</scope><scope>8BQ</scope><scope>8FD</scope><scope>FR3</scope><scope>JG9</scope></search><sort><creationdate>200502</creationdate><title>Irradiation creep and IASCC prediction method of PWR's core internal</title><author>KAMEYAMA, Masashi ; CHIGUSA, Naoki ; KUBO, Noboru ; KATAYAMA, Masaaki</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c2317-de25a163f9bed76cde6bf0dea9c08dadd5d43c79ada6a3a1a204ff4e99be74ee3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>jpn</language><creationdate>2005</creationdate><topic>Baffle former bolt</topic><topic>Barrel former bolt</topic><topic>Core internal</topic><topic>IASCC</topic><topic>Irradiation creep</topic><topic>Weld metal of barrel</topic><toplevel>online_resources</toplevel><creatorcontrib>KAMEYAMA, Masashi</creatorcontrib><creatorcontrib>CHIGUSA, Naoki</creatorcontrib><creatorcontrib>KUBO, Noboru</creatorcontrib><creatorcontrib>KATAYAMA, Masaaki</creatorcontrib><collection>CrossRef</collection><collection>Corrosion Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>METADEX</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Materials Research Database</collection><jtitle>QUARTERLY JOURNAL OF THE JAPAN WELDING SOCIETY</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>KAMEYAMA, Masashi</au><au>CHIGUSA, Naoki</au><au>KUBO, Noboru</au><au>KATAYAMA, Masaaki</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Irradiation creep and IASCC prediction method of PWR's core internal: Verification of "Inspection and Evaluation Guideline for Reactor Internals of PWR(Baffle Former Bolt)"</atitle><jtitle>QUARTERLY JOURNAL OF THE JAPAN WELDING SOCIETY</jtitle><date>2005-02</date><risdate>2005</risdate><volume>23</volume><issue>1</issue><spage>77</spage><epage>81</epage><pages>77-81</pages><issn>0288-4771</issn><eissn>2434-8252</eissn><abstract>PWR's core internals have aging due to IASCC (Irradiation Assisted Stress Corrosion Cracking). Although stress influences the occurrence of IASCC greatly, we have little data about PWR's irradiation creep which reduces stress. In this report, we assessed irradiation creep by using the removal torque of the baffle former bolts at the time of replacement. Then, we concluded that irradiation creep in PWR is approximately 50% of the irradiation creep in the fast breeder reactor. Moreover, we used this result to check the method for IASCC prediction method proposed in the last report which is applicable also to barrel former bolt and weld metal of barrel, and we confirmed the applicability of the IASCC prediction method for the actual plant.</abstract><pub>JAPAN WELDING SOCIETY</pub><doi>10.2207/qjjws.23.77</doi><tpages>5</tpages><oa>free_for_read</oa></addata></record> |
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source | J-STAGE (Japan Science & Technology Information Aggregator, Electronic) Freely Available Titles - Japanese; EZB-FREE-00999 freely available EZB journals |
subjects | Baffle former bolt Barrel former bolt Core internal IASCC Irradiation creep Weld metal of barrel |
title | Irradiation creep and IASCC prediction method of PWR's core internal: Verification of "Inspection and Evaluation Guideline for Reactor Internals of PWR(Baffle Former Bolt)" |
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