基于D-D中子源的乏燃料组件钚含量测量装置设计  

Design of a Plutonium Content Measurement Device for Spent Fuel Assemblies Based on D-D Neutronsource

作　　者：田园 李少伟[1] 何高魁 刘国荣[1] 周冬梅[1] 李井怀[1] 周浩[1] 梁庆雷[1] TIAN Yuan;LI Shaowei;HE Gaokui;LIU Guorong;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放射化学研究所,北京102413

出　　处：《核电子学与探测技术》2024年第2期200-207,共8页Nuclear Electronics & Detection Technology

摘　　要：为了满足国际社会上对于乏燃料组件内特种可裂变材料钚的保障监督需求,以持续提供核材料信息,研究乏燃料组件内钚含量测量的非破坏性分析技术显得尤为重要。本文采用主动法,以压水堆乏燃料组件作为测量对象,D-D中子作为质询中子源,开展了乏燃料组件钚含量测量装置的设计研究。采用MCNPX软件,基于最大化探测器计数率和使各探测器计数率尽量一致的目的,对测量装置中的中子管与探测器组件距离、中子管慢化材料及其厚度、探测器组件与中子管高度差、探测器组件中慢化体厚度等关键参数进行了模拟计算。此研究为中子质询乏燃料组件钚含量测量技术研究及实验验证打下了基础。In order to meet the international community's requirements of nuclear safeguards for the special fissionable material plutonium in spent fuel assemblies,and to provide nuclear material information continuously,it is particularly important to study non-destructive analysis techniques for measuring the plutonium content in spent fuel assemblies.This article adopts the active non-destructive assay,using pressurized water reactor spent fuel assemblies as the measurement object and D-D neutrons as active interrogation source,to carry out the design and research of a plutonium content measurement device for spent fuel assemblies.Using the MCNPX software,simulations were conducted on key parameters such as the distance between the neutron generator and the detector assembly,the moderator material and its thickness of the neutron generator,the height difference between the detector assembly and the neutron generator,and the moderator thickness of the detector assembly in the measurement device,with the aim of maximizing the detector counting rate and making the counting rates of each detector as consistent as possible.This study lays the foundation for the research and experiments of neutron interrogation technology for measuring plutonium content in spent fuel assemblies.

关 键 词：核保障 乏燃料 钚含量 中子质询 模拟计算 

分 类 号：TL811[核科学技术—核技术及应用]