高温气冷堆示范电站堆芯放射性总量计算方法

 高温气冷堆作为21世纪新一代先进核电站堆型，以安全性好、发电效率高、系统简化的优点越来越受到重视。中国第一个高温气冷堆示范电站（HTR-PM）在山东荣成石岛湾开始兴建，为准确分析核电站放射性对环境的影响，本文以KORIGEN程序为工具对高温气冷堆堆芯放射性总量计算方法进行了研究。首先为了使该程序能适应堆芯中子能谱变化的情况，对其进行了优化编译，并对数据库中的半衰期数据进行了更新和修正。在根据堆芯实际情况构造的流道模型条件下，得到了贴近堆芯真实情况的放射性总量，为高温气冷堆示范电站的安全审评、后续的安全管理和堆芯放射性核素物料衡算提供了基础和保证。

Calculations of Total Radioactivity Inventory in HTR-PM Reactor Core

As a new and advanced reactor system of nuclear power plants, the high temperature gas-cooled reactor has received more and more attention for its advantages in enhanced safety and highly economical and modular structure. In China, the first model power plant of the High Temperature Gas-cooled reactor (HTR-PM) is started its construction at Shidao Bay, Rongcheng, Shandong Province. This paper presents calculations of the total radioactivity inventory of HTR-PM core and the analysis of the environmental impact of the plant, using KORIGEN code. Some segments of the code were recompiled to consider the change of spectral indices in input data which reflects the realistic neutron situation in the reactor core. The half-life data of isotopes are updated and corrected. A reasonable flow-line model is built. Finally, the total inventory of radioactivity in HTR-PM reactor core is obtained, which approaches the actual one to provide a basis for safety analysis and management of HTR-PM, and for accounting of nuclear elements.