压水堆乏燃料组件中主要同位素含量分析计算  

Analysis of Main Isotope Content in Spent Fuel Assembly of Pressurized Water Reactor

作　　者：田园 刘国荣[1] 何高魁[1] 周冬梅[1] 李井怀[1] 周浩[1] 梁庆雷[1] TIAN Yuan;LIU Guorong;HE Gaokui;ZHOU Dongmei;LI Jinghuai;ZHOU Hao;LIANG Qinglei(China Institute of Atomic Energy,Beijing 102413,China)

机构地区：[1]中国原子能科学研究院,北京102413

出　　处：《核电子学与探测技术》2024年第3期515-522,共8页Nuclear Electronics & Detection Technology

摘　　要：绝大多数的特种可裂变材料钚均存在于商用乏燃料组件中,在核保障领域,对于乏燃料组件中钚含量的核实显得尤为重要。为分析计算乏燃料组件中易裂变核素钚的含量,以31组AFA-2G典型压水堆乏燃料组件为研究对象,通过分析核燃料在反应堆运行过程中的U-Pu循环燃耗链的特点,分析计算了乏燃料组件中主要同位素的含量和固有中子本底,同时利用蒙特卡罗模拟方法计算了239Pu等效质量的等效系数。本文工作为中子质询乏燃料组件易裂变核素含量非破坏性测量的方法研究及测量装置的设计打下了基础。Most of the special fissile material plutonium exists in the commercial spent fuel assembly.In the field of nuclear safeguards,the verification of the plutonium content in the spent fuel assembly is particularly important.In order to analyze the content of plutonium in spent fuel assembly,31 typical pressurized water reactor(AFA-2G)spent fuel assemblies were taken as the research object.By analyzing the characteristics of U-Pu cycle burnup chain of nuclear fuel during reactor operation,the content of main isotopes in spent fuel assembly and the inherent neutron background of spent fuel assembly were calculated and analyzed.At the same time,the efective mass of 239Pu was calculated by using the Monte Carlo simulation method.This study provides data support for the non-destructive analysis method of plutonium content in spent fuel and the design of measuring equipment.

关 键 词：核保障 乏燃料组件 同位素含量 239Pu等效质量 中子本底 

分 类 号：TL816[核科学技术—核技术及应用]