DC Field | Value | Language |
---|---|---|
dc.contributor.author | Ryu, Ho Jin | ko |
dc.contributor.author | Kim, Yeon Soo | ko |
dc.contributor.author | Hofman, G. L. | ko |
dc.date.accessioned | 2019-04-15T16:12:09Z | - |
dc.date.available | 2019-04-15T16:12:09Z | - |
dc.date.created | 2013-09-05 | - |
dc.date.issued | 2009-04 | - |
dc.identifier.citation | JOURNAL OF NUCLEAR MATERIALS, v.385, no.3, pp.623 - 628 | - |
dc.identifier.issn | 0022-3115 | - |
dc.identifier.uri | http://hdl.handle.net/10203/255637 | - |
dc.description.abstract | The microstructures of the product resulting from interaction between U-Mo fuel particles and the Al matrix in U-Mo/Al dispersion fuel are discussed. We analyzed the available characterization results for the Al matrix dispersion fuels from both the out-of-pile and in-pile tests and examined the difference between these results. The morphology of pores that form in the interaction products during irradiation is similar to the porosity previously observed in irradiation-induced amorphized uranium compounds. The available diffraction studies for the interaction products formed in both the out-of-pile and in-pile tests are analyzed. We have concluded that the interaction products in the U-Mo/Al dispersion fuel are formed as an amorphous state or become amorphous during irradiation, depending on the irradiation conditions. (C) 2009 Elsevier B.V. All rights reserved. | - |
dc.language | English | - |
dc.publisher | ELSEVIER SCIENCE BV | - |
dc.subject | POSTIRRADIATION EXAMINATION | - |
dc.subject | REACTION LAYER | - |
dc.subject | MO | - |
dc.subject | URANIUM | - |
dc.subject | REACTORS | - |
dc.subject | BEHAVIOR | - |
dc.subject | SYSTEM | - |
dc.subject | U3SI2 | - |
dc.title | Amorphization of the interaction products in U-Mo/Al dispersion fuel during irradiation | - |
dc.type | Article | - |
dc.identifier.wosid | 000265468100019 | - |
dc.identifier.scopusid | 2-s2.0-62349137925 | - |
dc.type.rims | ART | - |
dc.citation.volume | 385 | - |
dc.citation.issue | 3 | - |
dc.citation.beginningpage | 623 | - |
dc.citation.endingpage | 628 | - |
dc.citation.publicationname | JOURNAL OF NUCLEAR MATERIALS | - |
dc.identifier.doi | 10.1016/j.jnucmat.2009.01.306 | - |
dc.contributor.localauthor | Ryu, Ho Jin | - |
dc.contributor.nonIdAuthor | Kim, Yeon Soo | - |
dc.contributor.nonIdAuthor | Hofman, G. L. | - |
dc.type.journalArticle | Article | - |
dc.subject.keywordPlus | POSTIRRADIATION EXAMINATION | - |
dc.subject.keywordPlus | REACTION LAYER | - |
dc.subject.keywordPlus | MO | - |
dc.subject.keywordPlus | URANIUM | - |
dc.subject.keywordPlus | REACTORS | - |
dc.subject.keywordPlus | BEHAVIOR | - |
dc.subject.keywordPlus | SYSTEM | - |
dc.subject.keywordPlus | U3SI2 | - |
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