化学学报 ›› 2021, Vol. 79 ›› Issue (6): 716-728.DOI: 10.6023/A21020074 上一篇    下一篇

综述

人工放射性核素236U的分析方法进展及其应用

邵阳a,*(), 杨国胜b, 张继龙c, 罗敏a, 马玲玲a, 徐殿斗a   

  1. a 中国科学院高能物理研究所 北京市射线成像技术与装备工程技术研究中心 北京 100049
    b 国立研究开发法人量子科学技术研究开发机构 日本千叶市 2633-8555
    c 国家核安保技术中心 北京 102401
  • 投稿日期:2021-02-26 发布日期:2021-04-25
  • 通讯作者: 邵阳
  • 作者简介:

    邵阳, 助理研究员. 2019年毕业于中国科学院高能物理研究所, 获博士学位. 2018年以博士生身份在日本弘前大学辐射医疗综合研究所山田正俊课题组访问和学习一年. 主要研究方向为关键放射性核素分析方法开发与示踪应用研究.

    杨国胜, 日本量子科学技术研究开发机构, 主任研究员. 主要从事环境和人体中痕量人工放射性核素的分析方法开发、示踪及剂量评估等研究(137Cs、Te、226Ra、236U、237Np、239Pu、240Pu、129I等).

  • 基金资助:
    中国科学院重点部署项目(ZDRW-CN-2018-1); 国家自然科学基金(11875266); 国家自然科学基金(U1832212); 国家自然科学基金(U1932103); 中国科学院高能物理研究所谢家麟基金(E0546BU20B)

Progress and Application on the Analysis of Anthropogenic Radionuclide 236U

Yang Shaoa(), Guosheng Yangb, Jilong Zhangc, Min Luoa, Lingling Maa, Diandou Xua   

  1. a Beijing Engineering Research Center of Radiographic Techniques and Equipment, Institute of High Energy Physics, Chinese Academy of Sciences, Beijing 100049, China
    b National Institutes for Quantum and Radiological Science and Technology, Chiba, 263-8555, Japan
    c State Nuclear Security Technology Center, Beijing 102401, China
  • Received:2021-02-26 Published:2021-04-25
  • Contact: Yang Shao
  • Supported by:
    Key Deployment Projects of Chinese Academy of Sciences(ZDRW-CN-2018-1); National Natural Science Foundation of China(11875266); National Natural Science Foundation of China(U1832212); National Natural Science Foundation of China(U1932103); Xie Jialin Foundation, Institute of High Energy Physics, Chinese Academy of Sciences(E0546BU20B)

铀-236是一种重要的人工放射性核素, 是三种天然铀同位素之外可以应用在环境示踪、核应急、核取证以及核保障中的一种铀同位素. 人工236U主要是由核燃料235U经过中子照射后吸收中子产生, 因此, 不同“年龄”阶段核燃料中的236U和其他同位素的比值(指纹特征)截然不同. 同时不同反应堆类型中相应指纹特征也不尽相同. 通过监测核燃料、可疑核材料以及环境样品中不同236U/238U、236U/235U同位素比值等指纹特征即可确认反应堆运行状况、追溯核材料来源出处, 甚至可以开展放射性核污染物在环境中的迁移模拟等问题. 铀-236属于低丰度同位素, 其在核样品和环境样品中含量极低, 因此, 精确测定其同位素比值对236U在环境示踪、核应急、核取证以及核保障中的应用尤为重要. 本综述中, 作者总结了近年来痕量236U测定时样品前处理和检测分析技术的发展, 尤其着重于236U同位素比值的质谱检测技术的发展, 以及236U在核保障和环境中的示踪应用的研究进展. 最后, 对痕量236U检测和应用方面的研究提出展望.

关键词: 236U, 质谱分析, 前处理方法, 示踪应用, 核保障

Uranium-236 is an important anthropogenic radionuclide except for the three main natural uranium isotopes, which could be applied in the fields of environmental tracer, nuclear emergency response, nuclear forensics and nuclear safeguards. Artificial 236U is mainly generated through neuron absorption of nuclear fuel 235U after neuron irradiation. Therefore, the isotopic ratios of 236U with other uranium isotopes (fingerprints) are different at different nuclear fuel age. Also, the corresponding fingerprints are different in different types of nuclear reactor. The operation statue of nuclear reactor, the source of nuclear material and the migration of released radionuclides in environment could be studied by analyzing the isotopic ratios of 236U/238U and 236U/235U in the corresponding samples. Since 236U is a minor isotope and its concentration is extremely low in nuclear material and environmental samples, it is important to accurately analyze the isotopic ratios for its application in the environmental tracer, nuclear emergency response, nuclear forensics and nuclear safeguards. In this review, we summarized the development of sample pretreatment and analysis technologies for 236U measurement in recent years, especially focused on the development of 236U isotopic ratio analysis using mass spectrometry, and the research progress of 236U application in the fields of nuclear safeguards and environmental tracer was also reviewed. The research prospect for 236U analysis and application was also proposed.

Key words: 236U, mass spectrometry, pretreatment technique, tracer application, nuclear safeguards