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首页> 外文期刊>Journal of nuclear science and technology >Conceptual Design Study on Advanced Aqueous Reprocessing System for Fast Reactor Fuel Cycle
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Conceptual Design Study on Advanced Aqueous Reprocessing System for Fast Reactor Fuel Cycle

机译:快速反应堆燃料循环高级水后处理系统的概念设计研究

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The design study of an aqueous reprocessing system has been progressed for the feasibility study on commercialized fast reactor cycle systems in Japan. A simplified PUREX process, with the addition of a uranium crystallization step and a minor actinide (MA) recovery process was proposed as the NEXT process. For the simplified PUREX process and the SETFICS/TRUEX process for MA recovery, small-scale hot tests were conducted. The test results showed the decontamination factor (DF) of 10{sup}5 for the U, Pu and Np product was a reasonable target for the simplified PUREX process. Concerning to the Am and Cm product, the DF of rare earth elements (REs) and the other fission products (FPs) were over 10 and over 10{sup}2, respectively. For economical competitiveness, an aqueous reprocessing plant with the capacity of 200 tHM/yr cleared the target cost, while the plant with the capacity of 50 tHM/yr did not clear it. For efficient utilization of resources, the calculated U and TRU recovery of both plants was over 99 wt%. Using salt-free reagents and repeating concentration of waste solutions, the environmental impact was reduced. Pu was not isolated through the whole processes in the NEXT process in order to keep the proliferation resistance.
机译:对于日本商业化快速反应器循环系统的可行性研究,已经进行了水后处理系统的设计研究。提出了一种简化的PUREX工艺,并增加了铀结晶步骤和次要a系元素(MA)回收工艺,作为NEXT工艺。为了简化MA恢复的PUREX过程和SETFICS / TRUEX过程,进行了小规模的热测试。测试结果表明,U,Pu和Np产品的去污因子(DF)为10 {sup} 5是简化PUREX工艺的合理目标。关于Am和Cm积,稀土元素(REs)和其他裂变产物(FPs)的DF分别大于10和10 {sup} 2。为了获得经济竞争力,产能为200 tHM / yr的水处理厂清除了目标成本,而产能为50 tHM / yr的水处理厂没有清除目标成本。为了有效利用资源,两家工厂的U和TRU回收率均超过99 wt%。使用无盐试剂并重复浓缩废液,可以减少对环境的影响。为了保持抗扩散性,在NEXT工艺的整个过程中都没有分离出Pu。

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