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Long-lived fission product transmutation studies

机译:长寿命裂变产物trans变研究

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A systematic study on long-lived fission products (LLFPs) transmutation has been performed with the aim of devising an optimal strategy for their transmutation in critical or subcritical reactor systems and evaluating impacts on the geologic repository. First, Tc-99 and I-129 were confirmed to have highest transmutation priorities in terms of transmutability and long-term radiological risk reduction. Then, the transmutation potentials of thermal and fast systems for Tc-99 and I-129 were evaluated by considering a typical pressurized water reactor (PWR) core and a sodium-cooled accelerator transmutation of waste system. To determine the best transmutation capabilities, various target design and loading optimization studies were performed It was found that both Tc-99 and I-129 can be stabilized (i.e., zero net production) in the same PWR core under current design constraints by mixing Tc-99 with fuel and by loading CaI2 target pins mixed with ZrH2 in guide tubes, but the PWR option appears to have a limited applicability as a burner of legacy LLFP. In fast systems, loading of moderated LLFP target assemblies in the core periphery (reflector region) was found to be preferable from the viewpoint of neutron economy and safety. By a simultaneous loading of Tc-99 and I-129 target assemblies in the reflector region, the self-generated Tc-99 and I-129 as well as the amount produced by several PWR cores could be consumed at a cost of similar to10% increased fuel inventory. Discharge burnups of similar to29 and similar to37% are achieved for Tc-99 and I-129 target assemblies with an similar to5-yr irradiation period. Based on these results, the impacts of Tc-99 and I-129 transmutation on the Yucca mountain repository were assessed in terms of the dose rate. The current Yucca Mountain release evaluations do not indicate a compelling need to transmute Tc-99 and I-129 because the resulting dose rates fall well below current regulatory limits. However, elimination of the LLFP inventory could allow significant relaxation of the waste form and container performance criteria, with associated economic benefits. Therefore, some development of either specialized waste form or transmutation target for the LLFP is prudent, especially considering the potential accumulation of large LLFP inventory with sustained use of nuclear energy into the future. [References: 22]
机译:已经对长寿命裂变产物(LLFP)的mut变进行了系统研究,目的是为在临界或亚临界反应堆系统中进行their变的products变设计一种最佳策略,并评估其对地质储藏库的影响。首先,就可变性和长期放射风险降低而言,Tc-99和I-129被确认具有最高的trans变优先级。然后,通过考虑典型的压水堆(PWR)堆芯和废料系统的钠冷却促进剂trans变,评估了Tc-99和I-129的热和快速系统的the变潜力。为了确定最佳的capabilities变能力,进行了各种目标设计和负载优化研究,发现在当前设计约束下,通过混合Tc,Tc-99和I-129都可以在同一PWR堆芯中稳定(即零净产量)。 -99加燃料,并在导管中装入与ZrH2混合的CaI2目标销,但PWR选项作为传统LLFP燃烧器的适用性似乎有限。在快速系统中,从中子经济性和安全性的角度出发,发现在芯子外围(反射器区域)中加载适度的LLFP目标组件是优选的。通过在反射器区域中同时加载Tc-99和I-129目标组件,可以消耗自生成的Tc-99和I-129以及多个PWR磁芯产生的数量,其成本约为10%燃料库存增加。对于Tc-99和I-129靶组件,其照射期接近5年,放电燃耗达到29%到37%。根据这些结果,根据剂量率评估了Tc-99和I-129变异对丝兰山仓库的影响。当前的丝兰山释放评估并未表明迫切需要转换Tc-99和I-129,因为最终的剂量率大大低于当前的法规限制。但是,消除LLFP库存可以显着放宽废物形态和容器性能标准,并带来相关的经济利益。因此,谨慎地开发LLFP的专门废物形式或trans变目标是明智的,尤其是考虑到未来大型LLFP库存的潜在积累以及持续使用核能的情况。 [参考:22]

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