压水堆中Th-TRU环形燃料中子学性能初步分析

Preliminary Neutronic Analysis of Th-TRU Annular Fuel in Pressurized Water Reactors

  • 摘要: 为节约铀资源和减少高放废物的储存量,实现核能的可持续发展,利用钍基燃料嬗变高放废物成为各国研究的热点。基于我国完全自主研发的华龙一号(HPR1000)堆芯结构,结合环形燃料特点,利用蒙特卡罗程序对Th-TRU燃料物理性能、增殖性能、安全参数等进行研究并与UO2、(Th,233U)O2和(Th,U)O2进行比较。结果表明,相比于传统UO2燃料,(Th,233U)O2、(Th,U)O2、Th-TRU三种钍基燃料中子学性能均表现优异,尤其是Th-TRU燃料。Th-TRU燃料能够很大程度上提升堆芯中子学性能,并且能够有效嬗变次锕系(MA)核素,其中(Th,233U,4wt%TRU)O2的嬗变性能最佳;Th-TRU的燃料温度系数(FTC)、慢化剂温度系数(MTC)均保持在较大的安全范围内且能够有效降低功率峰因子,有望成为压水堆的候选燃料。本研究可为压水堆(PWR)中利用钍基燃料嬗变TRU提供一定参考。

     

    Abstract: To address uranium resource conservation and the reduction of high-level radioactive waste inventory for sustainable nuclear energy development, the utilization of thorium-based fuels for high-level radioactive waste transmutation has become a major global research focus. This work, based on China's fully indigenous HPR1000 reactor core design and leveraging annular fuel characteristics, employs Monte Carlo methods to investigate and analyze the neutronic performance—including physical properties, breeding performance, and safety parameters—of Th-TRU fuels. A comparative analysis with conventional UO2, (Th,233U)O2, and (Th,U)O2 fuels was conducted. Key findings reveal that all three thorium-based fuels—(Th,233U)O2, (Th,U)O2, and Th-TRU—exhibit superior neutronic performance compared to UO2, with Th-TRU fuels demonstrating the most significant enhancements. Th-TRU fuels substantially improve core neutronic performance and effectively transmute minor actinide (MA) nuclides, with (Th,233U, 4wt% TRU)O2 demonstrating the most effective transmutation capability. Furthermore, Th-TRU fuels maintain both fuel temperature coefficient (FTC) and moderator temperature coefficient (MTC) within wide safety margins and effectively reduce the power peaking factor, highlighting their potential as candidate fuels for pressurized water reactors (PWRs). This study provides insights into the utilization of thorium-based fuels for transmuting TRU in PWRs.

     

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