不同燃耗计算模型对商用压水堆乏燃料组件核素成分的影响分析  

Analysis of different burnup calculation models on nuclide components ofspent fuel assembly in commercial pressurized water reactor

作　　者：陈熙荣 谢金森[1,2] 于涛[1,2] 倪梓宁 邓年彪 邵增 谢浩然 Chen Xirong;Xie Jinsen;Yu Tao;Ni Zining;Deng Nianbiao;Shao Zeng;Xie Haoran(School of Nuclear Science and Technology,University of South China,Hengyang 421001,China;Virtual Simulation Experiment Teaching Center on Nuclear Energy and Technology,University of South China,Hengyang 421001,China;School of Resource Environment and Safety Engineering,University of South China,Hengyang 421001,China;China Nuclear Power Engineering Co.,Ltd,Beijing 100840,China)

机构地区：[1]南华大学核科学技术学院,湖南衡阳421001 [2]南华大学核能与核技术工程虚拟仿真实验教学中心,湖南衡阳421001 [3]南华大学资源环境与安全学院,湖南衡阳421001 [4]中国核电工程有限公司,北京100840

出　　处：《强激光与粒子束》2023年第5期146-152,共7页High Power Laser and Particle Beams

摘　　要：燃耗计算精度对提高乏燃料贮存效率有着重要影响,在应用燃耗信用制时,燃耗计算得到的核素成分偏差决定了乏燃料贮存的临界安全裕量。不同燃耗计算模型所得到的核素成分偏差各不相同,为提高燃耗计算精度,提出了一种装载不同燃料富集度的多组件燃耗计算模型,并使用不同燃耗计算模型分别对TMI-1反应堆NJ07OG组件中的6个样本进行了计算、对比和分析。结果表明,相比其他模型,考虑不同燃料富集度的多组件模型得到的235U、238U和239Pu等核素平均相对偏差更接近于零且6个样本的相对偏差分布更为平均。Burnup credit has an important impact on improving the efficiency of spent fuel storage.In theburnup credit,the burnup calculation model can affect the nuclide composition deviation,and the more accurate thenuclide composition,the lower the critical safety margin for spent fuel storage.To improve the accuracy of the burnupcalculation,a multi-assembly burnup calculation model loaded with different fuel enrichment is proposed in this paper.Six samples of TMI-1 reactor NJ07OG assemblies were calculated,compared and analyzed by using different burnupcalculation models.The results show that the average relative deviations of 235U,238U and 239Pu obtained from themulti-assembly burnup model with different fuel enrichment are closer to zero and the relative deviations are moreevenly distributed among the six samples than that of other models.

关 键 词：燃耗计算模型 乏燃料实验基准数据 核素成分偏差 燃耗信任制 

分 类 号：TL32[核科学技术—核技术及应用] TL329