摘要
为了估算内照射剂量,国际放射防护委员会(ICRP)推荐了多种放射性核素的参考人的生物动力学模型及其参数。ICRP还建议,若受照个体的剂量接近或大于个人年剂量限值时,应尽可能多的获得受照个体内照射监测资料,以便更准确地估算剂量;当受照个体接受了促排等医学处理,应采取个体的代谢资料估算剂量。本文以事故性过量摄入氚化水,且接受了促排医学处理的内污染为例,通过尿氚浓度的大量监测结果分析,得出了该受照个体的代谢资料。按此代谢资料估算的待积有效剂量为25.5 mSv,与国际原子能机构IAEA最终给出的参考值25.8 mSv仅相差1%。为了比较,也按照ICRP推荐的参考人的代谢资料估算了待积有效剂量,其结果为38.6 mSv,与参考值相差了48%。
In order to assess the internal exposure dose for radiation protection, reference biokinetic models and its parameters for radionuclide are recommended by International Commission on Radiological Protection（ICRP）. As an example in this paper, an individual biokinetic model for a tritiated water intake in an accident are developed based on the monitoring data of urine samples. The results show 25.5mSv of committed effective dose by developed individual biokinetic model, and 38.6mSv by reference model recommended by ICRP. The deviations with reference value given by IAEA are 1% and 48%, respectively.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2008年第6期87-90,共4页
Nuclear Power Engineering
关键词
氚内照射
剂量估算
氚化水
尿氚浓度
待积有效剂量
Tritium internal exposure, Dose assessment, Tritiated water, Tritium concentration in urine, Committed effective dose
