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dc.contributor.authorNakasuji, Toshikien
dc.contributor.authorMorishita, Kazunorien
dc.contributor.alternative中筋, 俊樹ja
dc.contributor.alternative森下, 和功ja
dc.date.accessioned2020-03-03T04:21:30Z-
dc.date.available2020-03-03T04:21:30Z-
dc.date.issued2020-
dc.identifier.issn0022-3131-
dc.identifier.urihttp://hdl.handle.net/2433/245879-
dc.description.abstractAn embrittlement correlation method is one of the most important techniques used to ensure the integrity of pressure vessel steels in nuclear power plants. In Japan, the embrittlement correlation method is being addressed in accordance with the Japan Electric Association Code (JEAC 4201), which was developed using actual measured data on the irradiation embrittlement of pressure vessel steels. In the present study, to develop more reliable methodologies, statistical arguments were made concerning the embrittlement data. With regard to a set of residual data defined in JEAC 4201 as a collection of differences between the measured and calculated ΔDBTT (ductile-to-brittle transition temperature shift) values, a statistical relationship between the population and samples was found, and then, the sampling errors in the mean values of the residuals were identified as key for establishing a more reliable correlation method. Using this relationship, it was noted that when predicting the amount of irradiation embrittlement for a particular plant using the JEAC 4201 correlation method, the deviation associated with sampling errors needed to be corrected. Based on this finding, a more appropriate interpretation was found for the so-called MC correction in JEAC 4201, and moreover, a new correction method was developed within the Bayesian estimation framework.en
dc.format.mimetypeapplication/pdf-
dc.language.isoeng-
dc.publisherTaylor and Francis Ltd.en
dc.rightsThis is an Accepted Manuscript of an article published by Taylor & Francis in Journal of Nuclear Science and Technology on 30 October 2020, available online: http://www.tandfonline.com/10.1080/00223131.2019.1676837.en
dc.rightsThe full-text file will be made open to the public on 30 October 2021 in accordance with publisher's 'Terms and Conditions for Self-Archiving'.en
dc.rightsこの論文は出版社版でありません。引用の際には出版社版をご確認ご利用ください。ja
dc.rightsThis is not the published version. Please cite only the published version.en
dc.subjectRadiation damageen
dc.subjectcalculationen
dc.subjectdatabaseen
dc.subjecterroren
dc.subjectLWR type reactoren
dc.subjectneutron irradiationen
dc.subjectnumerical analysisen
dc.titleStatistical arguments towards the development of an advanced embrittlement correlation method for reactor pressure vessel materialsen
dc.typejournal article-
dc.type.niitypeJournal Article-
dc.identifier.jtitleJournal of Nuclear Science and Technologyen
dc.identifier.volume57-
dc.identifier.issue3-
dc.identifier.spage312-
dc.identifier.epage322-
dc.relation.doi10.1080/00223131.2019.1676837-
dc.textversionauthor-
dc.addressGraduate School of Energy Science, Kyoto Universityen
dc.addressInstitute of Advanced Energy, Kyoto Universityen
dcterms.accessRightsopen access-
datacite.date.available2020-10-30-
datacite.awardNumber17J09649-
jpcoar.funderName日本学術振興会ja
jpcoar.funderName.alternativeJapan Society for the Promotion of Science (JSPS)en
出現コレクション:学術雑誌掲載論文等

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