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j.net.2015.12.001.pdf4.37 MBAdobe PDF見る/開く
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dc.contributor.authorKim, Wonkyeongen
dc.contributor.authorLee, Hyun Chulen
dc.contributor.authorPyeon, Cheol Hoen
dc.contributor.authorShin, Ho Cheolen
dc.contributor.authorLee, Deokjungen
dc.contributor.alternative卞 哲浩ja
dc.date.accessioned2018-06-12T01:23:33Z-
dc.date.available2018-06-12T01:23:33Z-
dc.date.issued2016-04-
dc.identifier.issn1738-5733-
dc.identifier.urihttp://hdl.handle.net/2433/231899-
dc.description.abstractAn accelerator-driven system consists of a subcritical reactor and a controllable external neutron source. The reactor in an accelerator-driven system can sustain fission reactions in a subcritical state using an external neutron source, which is an intrinsic safety feature of the system. The system can provide efficient transmutations of nuclear wastes such as minor actinides and long-lived fission products and generate electricity. Recently at Kyoto University Research Reactor Institute (KURRI; Kyoto, Japan), a series of reactor physics experiments was conducted with the Kyoto University Critical Assembly and a Cockcroft–Walton type accelerator, which generates the external neutron source by deuterium–tritium reactions. In this paper, neutronic analyses of a series of experiments have been re-estimated by using the latest Monte Carlo code and nuclear data libraries. This feasibility study is presented through the comparison of Monte Carlo simulation results with measurements.en
dc.format.mimetypeapplication/pdf-
dc.language.isoeng-
dc.publisherElsevier BVen
dc.rights© 2015, Published by Elsevier Korea LLC on behalf of Korean Nuclear Society. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).en
dc.subjectAccelerator-Driven Systemen
dc.subjectKyoto University Critical Assemblyen
dc.subjectMonte Carloen
dc.titleMonte Carlo Analysis of the Accelerator-Driven System at Kyoto University Research Reactor Instituteen
dc.typejournal article-
dc.type.niitypeJournal Article-
dc.identifier.jtitleNuclear Engineering and Technologyen
dc.identifier.volume48-
dc.identifier.issue2-
dc.identifier.spage304-
dc.identifier.epage317-
dc.relation.doi10.1016/j.net.2015.12.001-
dc.textversionpublisher-
dc.addressNuclear Engineering Division, Ulsan National Institute of Science and Technologyen
dc.addressVHTR Technology Development Division, Korea Atomic Energy Research Instituteen
dc.addressNuclear Engineering Science Division, Kyoto University Research Reactor Institute 1010en
dc.addressCore and Fuel Analysis Group, Korea Hydro & Nuclear Power Central Research Institute (KHNP-CRI)en
dc.addressNuclear Engineering Division, Ulsan National Institute of Science and Technologyen
dcterms.accessRightsopen access-
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