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首页> 外文期刊>Applied radiation and isotopes: including data, instrumentation and methods for use in agriculture, industry and medicine >The use of MOX caramel fuel mixed with Am-241, Am-242m and Am-243 as burnable absorber actinides for the MTR research reactors
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The use of MOX caramel fuel mixed with Am-241, Am-242m and Am-243 as burnable absorber actinides for the MTR research reactors

机译:使用MOX焦糖燃料与AM-241,AM-242M和AM-243混合为MTR研究反应器的可燃吸吸收器阳光苷

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The MOX (UO2 & PuO2) caramel fuel mixed with Am-241, Am-242m and Am-243 as burnable absorber actinides was proposed as a fuel of the MTR-22 MW reactor. The MCNP4C code was used to simulate the MTR-22 MW reactor and estimate the criticality and the neutronic parameters, and the power peaking factors before and after replacing its original fuel (U3O8-Al) by the MOX caramel fuel mixed with (241)AM, (242m)AM and Am-243 actinides. The obtained results of the criticality, the neutronic parameters, and the power peaking factors for the MOX caramel fuel mixed with Am-241, (242m)AM and (243)AM actinides were compared with the same parameters of the U3O8-Al original fuel and a maximum difference is -6.18% was found. Additionally, by recycling 2.65% and 2.71% plutonium and Am-241, Am-242m and (243)Arn actinides in the MTR-22 MW reactor, the level of U-235 enrichment is reduced from 4.48% to 3% and 2.8%, respectively. This also results in the reduction of the U-235 loading by 32.75% and 37.22% for the 2.65%, the 2.71% plutonium and Am-241, Am-242m and Am-243 actinides, respectively.
机译:用am-241,AM-242M和AM-243混合的MOX(UO2和PUO2)焦糖燃料作为可燃吸收器散曲线作为燃烧的燃烧剂作为MTR-22 MW反应器的燃料。 MCNP4C代码用于模拟MTR-22 MW反应器并估计临界性和中子参数,以及通过MOX焦糖燃料(241)AM更换原始燃料(U3O8-AL)之前和之后的功率峰值因子。 ,(242米)am和am-243 actinides。与AM-241(242M)和(243)和U3O8-AL原始燃料的相同参数进行比较了与AM-241混合的MOX焦糖燃料的临界焦糖燃料的功率峰值因子的所得结果最大差异是-6.18%。另外,通过再循环2.65%和2.71%的钚和AM-241,AM-242M和(243)ARN散落物在MTR-22 MW反应器中,U-235富集的水平从4.48%降低至3%和2.8% , 分别。这也导致u-235载荷减少32.75%,3.2.75%,2.65%,2.71%钚和am-241,am-242m和am-243散曲。

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