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학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2013.1
- 수록면
- 827 - 838 (12page)
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Interaction layer growth between U-Mo alloy fuel particles and Al in a dispersion fuel is a concern due to the volumeexpansion and other unfavorable irradiation behavior of the interaction product. To reduce interaction layer (IL) growth, asmall amount of Si is added to the Al. As a result, IL growth is affected by the Si content in the Al matrix. In order to predictIL growth during fabrication and irradiation, empirical models were developed. For IL growth prediction during fabrication andany follow-on heating process before irradiation, out-of-pile heating test data were used to develop kinetic correlations. Twoout-of-pile correlations, one for the pure Al matrix and the other for the Al matrix with Si addition, respectively, weredeveloped, which are Arrhenius equations that include temperature and time. For IL growth predictions during irradiation, theout-of-pile correlations were modified to include a fission-rate term to consider fission enhanced diffusion, and multiplicationfactors to incorporate the Si addition effect and the effect of the Mo content. The in-pile correlation is applicable for a pure Almatrix and an Al matrix with the Si content up to 8 wt%, for fuel temperatures up to 200 ºC, and for Mo content in the rangeof 6 – 10wt%. In order to cover these ranges, in-pile data were included in modeling from various tests, such as the USRERTR-4, -5, -6, -7 and -9 tests and Korea’s KOMO-4 test, that were designed to systematically examine the effects of thefission rate, temperature, Si content in Al matrix, and Mo content in U-Mo particles. A model converting the IL thickness tothe IL volume fraction in the meat was also developed.
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참고문헌 (22)
참고문헌 신청
E. Perez / 2009 / Interdiffusion in Diffusion Couples: U-Mo vs. Al and Al-Si / Proc. Int. Meeting on Reduced Enrichment for Research and Test Reactors (RERTR)
G. L. Hofman / 1999 / Initial assessment of radiation behavior of very-high-density low-enriched-uranium fuels / Proc. Int. Meeting on Reduced Enrichment for Research and Test Reac
G. L. Hofman / 2003 / Recent Observations at the Postirradiation Examination of Low-Enriched U-Mo Miniplates Irradiated to High Burnup / Proc. Int. Meeting on Reduced Enrichment fo
G. L. Hofman / 2004 / Post- Irradiation Analysis of Low Enriched U-Mo/Al Dispersion Fuel Miniplate Tests, RERTR 4 and 5 / Proc. Int. Meeting on Reduced Enrichment for Research and
G.L. Hofman / 1996 / Aluminum-U3Si2 Interdiffusion and Its Implications for the Performance of Fuel Operating at Higher Temperatures and Fission Rates / Proc. Int. Meeting on Redu
G. L. Hofman / 1999 / Initial assessment of radiation behavior of very-high-density low-enriched-uranium fuels / Proc. Int. Meeting on Reduced Enrichment for Research and Test Reac
G. L. Hofman / 2003 / Recent Observations at the Postirradiation Examination of Low-Enriched U-Mo Miniplates Irradiated to High Burnup / Proc. Int. Meeting on Reduced Enrichment fo
G. L. Hofman / 2004 / Post- Irradiation Analysis of Low Enriched U-Mo/Al Dispersion Fuel Miniplate Tests, RERTR 4 and 5 / Proc. Int. Meeting on Reduced Enrichment for Research and
G.L. Hofman / 1996 / Aluminum-U3Si2 Interdiffusion and Its Implications for the Performance of Fuel Operating at Higher Temperatures and Fission Rates / Proc. Int. Meeting on Redu
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