DC Field | Value | Language |
---|---|---|
dc.contributor.author | Kim, Yeon Soo | ko |
dc.contributor.author | Park, J. M. | ko |
dc.contributor.author | Lee, K. H. | ko |
dc.contributor.author | Yoo, B. O. | ko |
dc.contributor.author | Ryu, Ho Jin | ko |
dc.contributor.author | Ye, B. | ko |
dc.date.accessioned | 2015-04-06T05:52:25Z | - |
dc.date.available | 2015-04-06T05:52:25Z | - |
dc.date.created | 2014-12-09 | - |
dc.date.created | 2014-12-09 | - |
dc.date.issued | 2014-11 | - |
dc.identifier.citation | JOURNAL OF NUCLEAR MATERIALS, v.454, no.1-3, pp.238 - 246 | - |
dc.identifier.issn | 0022-3115 | - |
dc.identifier.uri | http://hdl.handle.net/10203/194717 | - |
dc.description.abstract | U-silicide or U-nitride coated U-Mo particle dispersion fuel in Al (U-Mo/Al) was in-pile tested to examine the effectiveness of the coating as a diffusion barrier between the U-7Mo fuel kernels and Al matrix. This paper reports the PIE data and analyses focusing on the effectiveness of the coating in terms of interaction layer (IL) growth and general fuel performance. The U-silicide coating showed considerable success, but it also provided evidence for additional improvement for coating process. The U-nitride coated specimen showed largely inefficient results in reducing IL growth. From the test, important observations were also made that can be utilized to improve U-Mo/Al fuel performance. The heating process for coating turned out to be beneficial to suppress fuel swelling. The use of larger fuel particles confirmed favorable effects on fuel performance. | - |
dc.language | English | - |
dc.publisher | ELSEVIER SCIENCE BV | - |
dc.subject | INTERACTION LAYER GROWTH | - |
dc.subject | MO DISPERSION | - |
dc.subject | DEGREES-C | - |
dc.subject | ALLOY | - |
dc.subject | SI | - |
dc.subject | INTERDIFFUSION | - |
dc.subject | URANIUM | - |
dc.subject | IRRADIATION | - |
dc.subject | ALUMINUM | - |
dc.subject | MATRIX | - |
dc.title | In-pile test results of U-silicide or U-nitride coated U-7Mo particle dispersion fuel in Al | - |
dc.type | Article | - |
dc.identifier.wosid | 000344428900034 | - |
dc.identifier.scopusid | 2-s2.0-84906773100 | - |
dc.type.rims | ART | - |
dc.citation.volume | 454 | - |
dc.citation.issue | 1-3 | - |
dc.citation.beginningpage | 238 | - |
dc.citation.endingpage | 246 | - |
dc.citation.publicationname | JOURNAL OF NUCLEAR MATERIALS | - |
dc.identifier.doi | 10.1016/j.jnucmat.2014.08.005 | - |
dc.contributor.localauthor | Ryu, Ho Jin | - |
dc.contributor.nonIdAuthor | Kim, Yeon Soo | - |
dc.contributor.nonIdAuthor | Park, J. M. | - |
dc.contributor.nonIdAuthor | Lee, K. H. | - |
dc.contributor.nonIdAuthor | Yoo, B. O. | - |
dc.contributor.nonIdAuthor | Ye, B. | - |
dc.type.journalArticle | Article | - |
dc.subject.keywordPlus | INTERACTION LAYER GROWTH | - |
dc.subject.keywordPlus | MO DISPERSION | - |
dc.subject.keywordPlus | DEGREES-C | - |
dc.subject.keywordPlus | ALLOY | - |
dc.subject.keywordPlus | SI | - |
dc.subject.keywordPlus | INTERDIFFUSION | - |
dc.subject.keywordPlus | URANIUM | - |
dc.subject.keywordPlus | IRRADIATION | - |
dc.subject.keywordPlus | ALUMINUM | - |
dc.subject.keywordPlus | MATRIX | - |
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