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DC Field | Value | Language |
---|---|---|
dc.citation.endPage | 152 | - |
dc.citation.startPage | 142 | - |
dc.citation.title | JOURNAL OF NUCLEAR MATERIALS | - |
dc.citation.volume | 465 | - |
dc.contributor.author | Kim, Yeon Soo | - |
dc.contributor.author | Jeong, G. Y. | - |
dc.contributor.author | Park, J. M. | - |
dc.contributor.author | Robinson, A. B. | - |
dc.date.accessioned | 2023-12-22T00:38:48Z | - |
dc.date.available | 2023-12-22T00:38:48Z | - |
dc.date.created | 2017-09-13 | - |
dc.date.issued | 2015-10 | - |
dc.description.abstract | Fission-induced swelling of U-Mo/Al dispersion fuel meat was measured using microscopy images obtained from post-irradiation examination. The data of reduced-size plate-type test samples and rodtype test samples were employed for this work. A model to predict the meat swelling of U-Mo/Al dispersion fuel was developed. This model is composed of several submodels including a model for interaction layer (IL) growth between U-Mo and Al matrix, a model for IL thickness to IL volume conversion, a correlation for the fission-induced swelling of U-Mo alloy particles, a correlation for the fission-induced swelling of IL, and models of U-Mo and Al consumption by IL growth. The model was validated using full-size plate data that were not included in the model development. | - |
dc.identifier.bibliographicCitation | JOURNAL OF NUCLEAR MATERIALS, v.465, pp.142 - 152 | - |
dc.identifier.doi | 10.1016/j.jnucmat.2015.06.006 | - |
dc.identifier.issn | 0022-3115 | - |
dc.identifier.scopusid | 2-s2.0-84935834808 | - |
dc.identifier.uri | https://scholarworks.unist.ac.kr/handle/201301/22683 | - |
dc.identifier.url | http://www.sciencedirect.com/science/article/pii/S0022311515300301 | - |
dc.identifier.wosid | 000364890300020 | - |
dc.language | 영어 | - |
dc.publisher | ELSEVIER SCIENCE BV | - |
dc.title | Fission induced swelling of U-Mo/Al dispersion fuel | - |
dc.type | Article | - |
dc.description.isOpenAccess | FALSE | - |
dc.relation.journalWebOfScienceCategory | Materials Science, Multidisciplinary; Nuclear Science & Technology | - |
dc.relation.journalResearchArea | Materials Science; Nuclear Science & Technology | - |
dc.description.journalRegisteredClass | scie | - |
dc.description.journalRegisteredClass | scopus | - |
dc.subject.keywordPlus | MO ALLOY FUEL | - |
dc.subject.keywordPlus | IRRADIATION PERFORMANCE | - |
dc.subject.keywordPlus | SI | - |
dc.subject.keywordPlus | RECRYSTALLIZATION | - |
dc.subject.keywordPlus | PLATES | - |
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