重水堆核电厂职业人员尿氚直接测量及内照射剂量估算  

Direct measurement of urine tritium and estimation of internal doses to personnel at pressurized heavy water reactor nuclear power plants

作　　者：陆丽燕 王孔钊 熊扣红 刘玉龙[3] Lu Liyan;Wang Kongzhao;Xiong Kouhong;Liu Yulong(Department Three of Health Physics,CNNC Nuclear Power Operations Management Co.,Ltd.,Haiyan 314300,China;Radiation Safety Institute,Nuclear Power Operations Research Institute,Shanghai 200216,China;Department of Oncology,Second Affiliated Hospital of Soochow University,Suzhou 215004,China)

机构地区：[1]中核核电运行管理有限公司保健物理三处,海盐314300 [2]核动力运行研究院辐射安全研究所,上海200120 [3]苏州大学附属第二医院肿瘤科,苏州215004

出　　处：《中华放射医学与防护杂志》2022年第7期544-548,共5页Chinese Journal of Radiological Medicine and Protection

基　　金：苏州大学附属第二医院学科建设托举工程核技术医学应用创新团队项目(XKTJHTD2021001)。

摘　　要：目的探讨重水堆电厂放射工作人员氚内照射监测及剂量估算优化方案。方法以CANDU-6型重水堆核电机组92名放射工作人员为观察对象,统计出淬灭指数(tSIE)的分布情况,挑选出10个淬灭指数tSIE最低160到最高460之间且分布均匀的样品制作空白尿样淬灭曲线,并与仪器自带淬灭曲线比较,优化尿氚测量体系相关性问题。氚内照射剂量估算方面,通过加拿大算法和国标算法的比较,优化调整剂量系数;通过稀释主热传输系统重水模拟实验,制作死时间校正曲线。结果通过氚内照射剂量估算的分析优化,确定剂量系数优化为4.8;制作了空白尿样淬灭曲线,通过对比发现,tSIE<200时偏差较大,证实了空白曲线的必要性;当测得尿中氚浓度高于2.4×10^(4) Bq/ml时,需要对尿样进行稀释处理,再进行测量来修正死时间的影响。结论通过优化氚内照射监测和剂量估算优化,不仅完善了重水堆电厂的集体剂量管理,还可以及时发现和处理人员非计划摄入氚,对重水堆电厂放射工作人员的辐射安全保障有着重要的作用。Objective To explore the optimization of tritium internal exposure monitoring and dose estimation for radiation workers at pressurized heavy water reactor nuclear power plants(PHWR NPPs).Methods A total of 92 radiation workers at Candu-6 PHWR NPPs were observed to calculate the distribution of quenching index(tSIE).Ten samples with tSIE values ranging from 160 to 460 were selected to make the blank urine quenching curve.By comparing with the quenching curve accompined with the equipment,the optimization of correlationship of urine tritium measurement system was carried out.In estimating tritium internal radiation dose,the dose coefficient was optimized and adjusted by comparing the Canadian algorithm with the national standard algorithm.Dead time correction curve was drawn by means of heavy water simulation experiment diluting main heat transfer system.Results Through the analysis and optimization of tritium internal dose estimation,the optimal dose coefficient was determined to be 4.8 and the quenching curve of blank urine sample was made.By comparison,it was found that the deviation was larger when tSIE<200,which confirmed the necessity of blank curve.When the tritium concentration in urine was higher than 2.4×10^(4) Bq/ml,the urine sample needed to be diluted and then measured to correct the effect of death time.Conclusions By optimizing both tritium internal exposure monitoring and dose estimation,not only the collective dose management can be improved,but also the unplanned tritium intake can be detected and treated in time,which plays an important role in ensuring the protection and safety of the radiation workers at PHWR NPPs.

关 键 词：氚 内照射 监测 剂量估算 死时间 

分 类 号：R144.1[医药卫生—公共卫生与预防医学]