Irradiation Performance of U-Mo Monolithic Fuel

M.K. Meyer; J.GAN; D.D. KEISER; E. PEREZ; A. ROBINSON; D.M. WACHS; N. WOOLSTENHULME; G.L. Hofman; Y. S. Kim

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자료유형: 학술저널

저자정보: M.K. Meyer J.GAN D.D. KEISER E. PEREZ A. ROBINSON D.M. WACHS N. WOOLSTENHULME G.L. Hofman Y. S. Kim

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제46권 제2호

발행연도: 2014.1

수록면: 169 - 182 (14page)

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High-performance research reactors require fuel that operates at high specific power to high fission density, but atrelatively low temperatures. Research reactor fuels are designed for efficient heat rejection, and are composed of assemblies ofthin-plates clad in aluminum alloy. The development of low-enriched fuels to replace high-enriched fuels for these reactorsrequires a substantially increased uranium density in the fuel to offset the decrease in enrichment. Very few fuel phases havebeen identified that have the required combination of very-high uranium density and stable fuel behavior at high burnup. UMoalloys represent the best known tradeoff in these properties. Testing of aluminum matrix U-Mo aluminum matrixdispersion fuel revealed a pattern of breakaway swelling behavior at intermediate burnup, related to the formation of amolybdenum stabilized high aluminum intermetallic phase that forms during irradiation. In the case of monolithic fuel, thisissue was addressed by eliminating, as much as possible, the interfacial area between U-Mo and aluminum. Based on scopingirradiation test data, a fuel plate system composed of solid U-10Mo fuel meat, a zirconium diffusion barrier, and Al6061cladding was selected for development. Developmental testing of this fuel system indicates that it meets core criteria for fuelqualification, including stable and predictable swelling behavior, mechanical integrity to high burnup, and geometric stability. In addition, the fuel exhibits robust behavior during power-cooling mismatch events under irradiation at high power

#U-Mo #Monolithic Fuel #Research Reactor #Dispersion #Irradiation Testing #Low-enriched Uranium

참고문헌 (29)

참고문헌 신청

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