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首页> 外文期刊>Annals of nuclear energy >The closed thorium-transuranic fuel cycle in reduced-moderation PWRs and BWRs
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The closed thorium-transuranic fuel cycle in reduced-moderation PWRs and BWRs

机译：减缓压水堆和压水堆中封闭的trans-超铀燃料循环

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Multiple recycle of long-lived actinides has the potential to greatly reduce the required storage time for spent nuclear fuel or high level nuclear waste. This is generally thought to require fast reactors as most transuranic (TRU) isotopes have low fission probabilities in thermal reactors. Reduced-moderation LWRs are a potential alternative to fast reactors with reduced time to deployment as they are based on commercially mature LWR technology. Thorium (Th) fuel is neutronically advantageous for TRU multiple recycle in LWRs due to a large improvement in the void coefficient. If Th fuel is used in reduced-moderation LWRs, it appears neutronically feasible to achieve full actinide recycle while burning an external supply of TRU, with related potential improvements in waste management and fuel utilization. In this paper, the fuel cycle of TRU-bearing Th fuel is analysed for reduced-moderation PWRs and BWRs (RMPWRs and RBWRs). RMPWRs have the advantage of relatively rapid implementation and intrinsically low conversion ratios, which is desirable to maximize the TRU burning rate. However, it is challenging to simultaneously satisfy operational and fuel cycle constraints. An RBWR may potentially take longer to implement than an RMPWR due to more extensive changes from current BWR technology. However, the harder neutron spectrum can lead to favourable fuel cycle performance. A two-stage TRU burning cycle, where the first stage is Th-Pu MOX in a conventional PWR feeding a second stage continuous burn in RMPWR or RBWR, is technically reasonable, although it is more suitable for the RBWR implementation. In this case, the fuel cycle performance is relatively insensitive to the discharge burn-up of the first stage.
机译：长寿命act系元素的多次回收具有极大地减少乏核燃料或高含量核废料所需的存储时间的潜力。通常认为这需要快速反应堆，因为大多数超铀（TRU）同位素在热反应堆中的裂变概率均较低。轻度适度的轻水堆基于商业上成熟的轻水堆技术，是潜在的快速反应堆替代品，可缩短部署时间。由于空隙系数的大幅提高，void燃料在LWR的TRU多次循环中具有中子优势。如果将Th燃料用于减量轻型轻水堆，在燃烧外部供应的TRU的同时实现act系元素的完全回收在中子上似乎是可行的，同时在废物管理和燃料利用方面也有潜在的改进。在本文中，对TRU轴承Th燃料的燃料循环进行了分析，以得出减慢的PWR和BWR（RMPWR和RBWR）。 RMPWR具有实现速度相对较快和转换率本质上较低的优势，这是使TRU燃烧速率最大化的理想选择。然而，同时满足操作和燃料循环约束是挑战性的。由于当前BWR技术的更广泛变化，RBWR的实现时间可能比RMPWR更长。但是，较硬的中子光谱会导致良好的燃料循环性能。从技术上讲，两步式TRU燃烧循环是合理的，尽管第一步为常规PWR中的Th-Pu MOX，然后再向RMPWR或RBWR中的第二步连续燃烧，但它更适合RBWR实施。在这种情况下，燃料循环性能对第一级的排气燃耗相对不敏感。

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