同位素2026，Vol.39Issue(1)：14-23,10.DOI:10.7538/tws.2025.youxian.070
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
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.关键词
铀资源/华龙一号/钍基燃料/超铀核素/蒙特卡罗程序Key words
uranium resources/HPR1000/thorium-based fuel/transuranic nuclides/Monte Carlo code分类
能源科技引用本文复制引用
毛俊杰,叶滨,AYODEJI Adebisi A.Ala..压水堆中Th-TRU环形燃料中子学性能初步分析[J].同位素,2026,39(1):14-23,10.基金项目
国家自然科学基金项目(12005178) （12005178）
四川省科学基金项目(2025NSFSC2085) （2025NSFSC2085）
四川省大学生创新训练计划项目(S202510619010) （S202510619010）
