目的 乏燃料后处理厂中,作业环境工况复杂,开放性操作较多,使用机械臂操作时需要使用窥视窗直观的进行操作内容,为确保工作人员安全,同时提升窥视窗的使用寿命,有必要开展对窥视窗选材的优化分析。方法 本文结合典型核电厂的深燃耗乏燃料组件的源项特征,对窥视窗的选材型号分析研究,利用蒙特卡罗方法程序建立计算模拟,分析不同窥视窗玻璃组合的防护性能并评估使用寿命。结果 通过分析采用不同玻璃排列组合窥视窗的屏蔽性能和耐辐照表现,提出可以长期适应热室中高辐射场所使用的窥视窗材料选择和布置方式。结论 基于热室高辐射作业带来的复杂辐射环境,窥视窗的材料应尽量选择辐照稳定性强的玻璃靠近热室侧,同时尽可能增加数量。这样,既可显著提升整体窥视窗的寿命,又可在寿期内降低工作人员应更换窗体导致的频次,从而大幅降低集体剂量。
Abstract
In a nuclear fuel reprocess plant (NFRP), the operating environment features complex working conditions and a large number of open operation processes. When using a robotic arm for operation, a sight window is required to directly observe the operation process. To ensure the safety of staff and extend the service life of the sight window, it is necessary to carry out optimization analysis on the material selection of the sight window. Based on the source term characteristics of deep burn-up spent fuel assemblies in typical nuclear power plants, analytical research on the material selection models of sight windows was conducted, computational simulations was established through the Monte Carlo method program, the shielding performance of different sight window glass combination was analyzed, and their service life was assessed. By analyzing the shielding performance and radiation resistance of sight windows with different glass permutation and combination, a material selection and layout scheme for sight windows that can be used for a long time in high-radiation areas of hot cells was proposed. Considering the complex radiation environment caused by high-radiation operations in hot cells, for the materials of sight windows, glasses with strong irradiation stability should be placed as close to the hot cell side as possible, and the number of such glass layers should be increased as much as possible. In this way, the overall service life of the sight window can be significantly extended, and the frequency of personnel entering the radiation area to replace the window panel during its service life can be reduced, thus greatly lowering the collective radiation dose.
关键词
窥视窗 /
材料屏蔽性能评估 /
不同排列组合性能分析
Key words
sight window /
shielding performance evaluation /
performance analysis for different permutation and combination
{{custom_sec.title}}
{{custom_sec.title}}
{{custom_sec.content}}
参考文献
[1] 韦悦周, 吴艳, 李辉波. 最新核燃料循环[M]. 上海: 上海交通大学出版社, 2016: 225-292.
WEI Y Z, WU Y, LI H B.Nuclear Fuel Cycle[M]. Shanghai: Shanghai Jiao Tong University Press, 2016: 225-292.
[2] IAEA. Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards[R]. IAEA GSR Part 3. Vienna: IAEA 2011: 117.
[3] 张晔, 陈宗欢, 高桂玲等. 乏燃料后处理厂复合型生物屏蔽门的屏蔽性能分析[J]. 中国科技成果, 2022(12): 40-50.
ZHANG Y, CHEN Z H, GAO G L, et al.Shielding Performance Analysis on Biological Shielding Gate in the NFRP[J]. China Science and Technology Achievement, 2022(12): 40-50.
[4] BOWMAN S M, LEAL L C.Automatic Rapid Processing For Spent Fuel Depletion, Decay, And Soutce Term Analysis[M]. Tennessee: Oak Riadge National Laboatory, 2006.
[5] 李德平, 潘自强. 辐射防护手册(第一分册)辐射源与屏蔽[M]. 北京: 原子能出版社, 1987: 128-130.
LI D P, PAN Z Q. Radiation Protection Manual.Volume 1, Radiation Sources and Shielding[M]. Beijing: Atomic Energy Press, 1987: 128-130.
[6] 刘运祚. 常用放射性核素衰变纲图[M]. 北京: 原子能出版社, 1982: 171-172.
LIU Y Z.Decay Schemes of Commonly Used Radionuclides [M]. Beijing: Atomic Energy Press, 1982: 171-172.
[7] 张昌杰, 马占营, 李坤. 屏蔽箱室内窥视窗玻璃选材研究[J]. 辐射防护通讯, 2024(4): 72-80.
ZHANG C J, MA Z Y, LI K.Study on Glass Material Selection for Shielded Cell Observation Windows[J]. Radiation Protection Bulletin, 2024(4): 72-80.
[8] 中华人民共和国第二机械工业部. EJ36-75窥视窗防、耐辐射玻璃板[S]. 北京: 中华人民共和国第二机械工业部, 1975.
The Second Ministry of Machine Building Industry of the People’s Republic of China. EJ36-1975 Radiation- Shielding and Radiation-Resistant Glass Plates for Observation Windows[S]. Beijing: The Second Ministry of Machine Building Industry of the People’s Republic of China, 1975.
[9] ICRP. Conversion Coefficients For use in Radiological Protection against External Radiation[R].Oxford: Pergamon Press, 1996.
[10] ICRP. 国际辐射防护委员会第74号出版物[M]. 陈丽姝, 柴政文, 译. 北京: 原子能出版社, 1995.
ICRP. ICRP Publication 74[M]. CHEN L S, CAI Z W, translated. Beijing: Atomic Energy Press, 1995.
[11] 王巍, 杨海东, 扬天伟, 等. 60 Coγ射线对铅玻璃性能影响研究[J]. 电子学与探测技术 2025(6): 65-70.
WANG W, YANG H D, YANG T W, et al.Study on the Effects of Cobalt-60 Gamma Rays on the Properties of Lead Glass[J]. Electronics and Detection Technology, 2025(6): 65-70.
[12] 郭英蕾, 张建, 葛良全. 钴-60操作热室窥视窗设计及性能分析[J]. 同位素, 2020(8): 82-94.
GUO Y L, ZHANG J, GE L Q.Design and Performance Analysis of the Observation Window for Cobalt-60 Operation Hot Cell[J]. Isotopes, 2020(8): 82-94.
[13] 霍雷, 刘剑利, 马永和. 辐射剂量与防护[M]. 北京: 电子工业出版社, 2015.
HUO L, LIU J L, MA Y H.Radiation Dose and Protection [M]. Beijing: Publishing House of Electronics Industry, 2015.
[14] 曹良志, 谢仲生, 李云召. 近代核反应堆物理分析[M]. 北京: 中国原子能出版社, 2017: 301-315.
CAO L Z, XIE Z S, LI Y Z.Modern Nuclear Reactor Physics Analysis [M]. Beijing: China Atomic Energy Press, 2017: 301-315.
[15] 中华人民共和国国家质量监督检验检疫总局. GB 18871-2002, 电离辐射防护与辐射源安全基本标准[S]. 北京: 中国标准出版社, 2002.
General Administration of Quality Supervision, Inspection and Quarantine of the People's Republic of China, GB 18871-2002, Basic Standard for Ionizing Radiation Protection and Radiation Source Safety[S] GB 18871-2002, Basic Standard for Ionizing Radiation Protection and Radiation Source Safety[S]. Beijing: Standards Press of China, 2002.
PDF(1315 KB)
渝公网安备 50010702501716号 渝ICP备15012534号-2
