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Rapid Transmutation of High-Level Nuclear Wastes in a Catalyzed Fusion-Driven System

机译:催化聚变驱动系统中高级核废料的快速Trans变

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The aim of this study is to investigate the high-level waste (HLW) transmutation potential of fusion-driven transmuter (FDT) based on catalyzed D-D fusion plasma for various fuel fractions. The Minor actinide (MA) (~(237)Np, ~(241)Am, ~(243)Am and ~(244)Cm) and long-lived fission product (LLFP) (~(99)Tc, ~(129)I and ~(135)Cs) nuclides discharged from high burn-up pressured water reactor-mixed oxide spent fuel are considered as the HLW. The volume fractions of the MA and LLFP are raised from 10 to 20% stepped by 2% and 10 to 80% stepped by 5%, respectively. The transmutation analyses have been performed for an operation period (OP) of up to 6 years by 75% plant factor (η) under a first-wall neutron load (P) of 5 MW/m~2 by using two different computer codes, the XSDRNPM/SCALE4.4a neutron transport code and the MCNP4B Monte Carlo code. The numerical results bring out that the considered FDT has a high neutronic performance for an effective and rapid transmutation of MA and LLFP as well as the energy generation along the OP.
机译:这项研究的目的是研究基于催化D-D聚变等离子体的各种燃料馏分的聚变驱动变换器(FDT)的高放废物(HLW)转化潜力。次act系元素(MA)(〜(237)Np,〜(241)Am,〜(243)Am和〜(244)Cm)和长寿命裂变产物(LLFP)(〜(99)Tc,〜(129从高燃尽压力水反应堆混合氧化物乏燃料中排出的I和〜(135)Cs核素被认为是高放废物。 MA和LLFP的体积分数分别从10%提高到20%(逐步提高2%)和10%到80%(逐步提高5%)。通过使用两个不同的计算机代码,在5 MW / m〜2的第一壁中子负荷(P)下,通过75%的工厂因子(η)对长达6年的运行时间(OP)进行了analyzes变分析, XSDRNPM / SCALE4.4a中子传输代码和MCNP4B蒙特卡洛代码。数值结果表明,所考虑的FDT对于MA和LLFP的有效和快速trans变以及沿OP的能量产生具有高中子性能。

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