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Study on fission blanket fuel cycling of a fusion-fission hybrid energy generation system

机译：聚变裂变混合能源发电系统的裂变毯燃料循环研究

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摘要

This paper presents a preliminary study on neutron physics characteristics of a light water cooled fission blanket for a new type subcritical fusion-fission hybrid reactor aiming at electric power generation with low technical limits of fission fuel. The major objective is to study the fission fuel cycling performance in the blanket, which may possess significant impacts on the feasibility of the new concept of fusion-fission hybrid reactor with a high energy gain (M) and tritium breeding ratio (TBR). The C0UPLE2 code developed by the Institute of Nuclear and New Energy Technology of Tsinghua University is employed to simulate the neutronic behaviour in the blanket. COUPLE2 combines the particle transport code MCNPX with the fuel depletion code 0RIGEN2. The code calculation results show that soft neutron spectrum can yield M > 20 while maintaining TBR > 1.15 and the conversion ratio of fissile materials CR > 1 in a reasonably long refuelling cycle (>five years). The preliminary results also indicate that it is rather promising to design a high-performance light water cooled fission blanket of fusion-fission hybrid reactor for electric power generation by directly loading natural or depleted uranium if an ITER-scale tokamak fusion neutron source is achievable.
机译：本文针对新型亚临界聚变裂变混合反应堆，以低裂变燃料技术极限的发电为目标，对轻水冷却裂变层的中子物理特性进行了初步研究。主要目的是研究毯子中裂变燃料的循环性能，这可能对具有高能量增益（M）和tri增殖比（TBR）的聚变裂变混合堆新概念的可行性产生重大影响。清华大学核能与新能源技术研究所开发的C0UPLE2代码用于模拟毯子中的中子行为。 COUPLE2将粒子传输代码MCNPX与燃料消耗代码0RIGEN2结合在一起。代码计算结果表明，在相当长的加油周期（> 5年）内，软中子谱可产生M> 20，同时保持TBR> 1.15，裂变材料CR的转化率CR> 1。初步结果还表明，如果可以实现ITER规模的托卡马克聚变中子源，则可以通过直接装载天然铀或贫化铀来设计用于聚变裂变混合反应堆的高性能轻水冷却裂变毯，用于发电。

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  • 来源
    《Nuclear fusion》 |2011年第10期|p.103011.1-103011.5|共5页
  • 作者

    Z. Zhou; Y. Yang; H. Xu;

  • 作者单位

    Institute of Nuclear and New Energy Technology of Tsinghua University, Beijing, People's Republic of China,State Nuclear Power Technology R&D Centre, Beijing, People's Republic of China;

    Institute of Nuclear and New Energy Technology of Tsinghua University, Beijing, People's Republic of China;

    State Nuclear Power Technology R&D Centre, Beijing, People's Republic of China;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
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