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首页> 外文会议>International conference on the physics of reactors;PHYSOR 2010 >BREED-AND-BURN DEPLETED URANIUM IN FAST REACTORS WITHOUT ACTINIDES SEPARATION
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BREED-AND-BURN DEPLETED URANIUM IN FAST REACTORS WITHOUT ACTINIDES SEPARATION

机译：快速分离反应器中的稀有和未消耗的铀

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Using multi-recycling without actinides separation it is possible to establish a breed-and-burn mode of operation in fast reactor cores that are fed with depleted uranium without violating any of the presently accepted radiation damage constraints. The maximum burnup attainable using this mode of operation in large fast reactors is found to be 55%. This corresponds to two orders of magnitude increase in the uranium ore utilization relative to that achievable in once-through LWRs. The energy value of the depleted uranium accumulated worldwide, when used in the proposed breed-and-burn energy system, is equivalent to 3000 years of the present global nuclear capacity. Relative to LWR operating with the once-through fuel cycle, the fuel discharged from the breed-and-burn fast reactor and fuel cycle hereby proposed features, per unit of electricity generated: (a) -40% the amount of TRU and Pu; (b) -10% the inventory of ~(237)Np and its precursors; (c) -12% of the decay heat from TRU one year following discharge; (d) -28% of the radiotoxicity; (e) -7% the neutron emission rate one year following discharge. The fraction of the fissile isotopes in the discharged plutonium is comparable but the decay heat and neutron emission rate per unit mass of discharged plutonium are nearly half as large. The proposed mode of operation is expected to improve the economics and the proliferation resistance and, hence, may justify sooner deployment of fast reactors. The deployment of the suggested fast reactor system will constitute a significant step forward towards sustainable nuclear energy.
机译：使用不进行act系元素化合物分离的多次循环，有可能在供给贫铀的快速反应堆堆芯中建立起“加温燃烧”的运行模式，而不会违反任何目前公认的辐射损害限制条件。使用这种操作模式在大型快堆中可获得的最大燃耗为55％。相对于一次过的轻水堆，铀矿石利用量增加了两个数量级。在提议的繁殖和燃烧能源系统中使用时，全世界累积的贫化铀的能源价值相当于目前全球核能的3000年。相对于以一次通过的燃料循环运行的轻水堆，从燃放快堆反应堆排出的燃料和由此得出的燃料循环的特征是，每单位发电量：（a）TRU和Pu量的-40％; （b）〜（237）Np及其前体的存量的-10％; （c）排放后一年，来自TRU的衰减热的-12％; （d）-28％的放射毒性; （e）排放后一年的中子发射率为-7％。排出的p中的易裂变同位素的分数是可比较的，但是每单位质量排出的p的衰变热和中子发射率几乎是其一半。预计拟议的运行方式将改善经济性和抗扩散性，因此，可证明较早部署快速反应堆是合理的。建议的快速反应堆系统的部署将是朝着可持续核能迈出的重要一步。

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