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dc.contributor.authorKatasho, Yumien
dc.contributor.authorYasuda, Koujien
dc.contributor.authorOishi, Tetsuoen
dc.contributor.authorNohira, Toshiyukien
dc.contributor.alternative片所, 優宇美ja
dc.contributor.alternative安田, 幸司ja
dc.contributor.alternative野平, 俊之ja
dc.date.accessioned2020-10-30T01:28:31Z-
dc.date.available2020-10-30T01:28:31Z-
dc.date.issued2021-01-
dc.identifier.issn0022-3115-
dc.identifier.urihttp://hdl.handle.net/2433/255843-
dc.description.abstractThe electrochemical reduction of vitrified nuclear waste simulant glass produced by melting oxides of 33 different elements, including Si and four types of long-lived fission product elements (Cs, Zr, Pd, and Se), was investigated in molten CaCl₂ at 1103 K. Before the experiment, potential−pO²⁻ diagrams were constructed from the thermodynamic data to predict the behaviors of the constituent elements during the electrochemical reduction. In the first experiment, small crucible electrodes containing approximately 100 mg of the simulant were electrolyzed at 0.6–1.1 V vs. Ca²⁺/Ca. X-ray diffraction analysis confirmed that SiO₂ was reduced to Si. In addition, the formation of XB₆ (X = Ca, Si, or rare earth elements (REEs)) was confirmed. In the second experiment, a large crucible electrode containing approximately 10 g of the simulant was galvanostatically reduced at −2 A for 5 h. The distribution ratios of the constituent elements to the solid product and to the molten salt were calculated from the result of composition analysis using inductively coupled plasma atomic emission spectrometry and mass spectrometry. In particular, four types of long-lived fission product elements (Cs, Zr, Pd, and Se) were investigated. Consequently, alkali and alkaline earth elements, including Cs, were dissolved into the molten salt. Si mostly remained in the solid product as elemental silicon. Most of the other elements, including Zr and Pd, were also found in the solid product. Se and Zn were indicated to partially evaporate depending on the duration of electrolysis.en
dc.format.mimetypeapplication/pdf-
dc.language.isoeng-
dc.publisherElsevier BVen
dc.rights© 2021. This manuscript version is made available under the CC-BY-NC-ND 4.0 license http://creativecommons.org/licenses/by-nc-nd/4.0/,en
dc.rightsThe full-text file will be made open to the public on 1 January 2023 in accordance with publisher's 'Terms and Conditions for Self-Archiving'.en
dc.rightsThis is not the published version. Please cite only the published version.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.subjectMolten salten
dc.subjectVitrified radioactive wasteen
dc.subjectElectrochemical reductionen
dc.subjectPotential−pO²⁻en
dc.subjectdiagramen
dc.titleElectrochemical reduction behavior of vitrified nuclear waste simulant in molten CaCl₂en
dc.typejournal article-
dc.type.niitypeJournal Article-
dc.identifier.jtitleJournal of Nuclear Materialsen
dc.identifier.volume543-
dc.relation.doi10.1016/j.jnucmat.2020.152578-
dc.textversionauthor-
dc.identifier.artnum152578-
dc.addressInstitute of Advanced Energy, Kyoto University・Global Zero Emission Research Center, National Institute of Advanced Industrial Science and Technology (AIST)en
dc.addressAgency for Health, Safety and Environment, Kyoto University・Department of Fundamental Energy Science, Graduate School of Energy Science, Kyoto Universityen
dc.addressGlobal Zero Emission Research Center, National Institute of Advanced Industrial Science and Technology (AIST)en
dc.addressInstitute of Advanced Energy, Kyoto Universityen
dcterms.accessRightsopen access-
datacite.date.available2023-01-01-
datacite.awardNumber17J08901-
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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