核电站氚的排放量及浓度限值比较分析

氚是核电站运行过程中向环境中排放较大的放射性核素之一,控制核设施中氚的产生和排放量越来越引起人们的重视。本文通过分析核电站产生氚的主要途径,结合国际上的运行经验参数,对比分析了不同国家、不同堆型核电站氚的排放量和浓度限值。分析结果表明:三十年间,全球核电站流出物中气态氚的排放量显著高于液态氚,重水堆是各堆型核电站中氚排放的主要贡献者,也是氚排放所致公众剂量的主要来源。为了更加有效的控制氚的排放,法国等国家核安全监管机构根据电站的装机容量、排放工艺、堆型等制定了各自国家核电站氚的年排放总量限值;加拿大等国的监管机构根据剂量限值制定了导出排放限值,该值的优点是便于审查核电站正常运行时氚的排放量;其它核电国家则是以剂量限值的形式提出了氚的排放限值。

Analysis of Tritium Releases and Concentration Limitation from NPPs

Tritium is the large amount of radionuclide released from nuclear power plant under normal operation. It has attracted more and more attentions to control tritium emissions. Based on the international operation practice, the release and concentration limitation of tritium from different countries and different types NPPs were analyzed. The results indicate gas tritium emissions significantly higher liquid tritium from NPPs effluence, Heavy Water Reactor(HWR) is a major contributor to tritium emissions, also be the main source of public dose from tritium. In order to control tritium more effectively, based on installed capacity, discharge technical, reactor type, the government''s nuclear safety regulation,such as France, established tritium annual concentration limitation, and the safety regulation of Canada and other countries made the derived release limit, which facilitates censorship the tritium emissions, other country proposed release limit in dose limit form.