摘要
本文对核素在反应堆内部的产生、转移和释放过程进行了分析研究,计算了一回路冷却剂中放射性核素的浓度。并考虑了一回路系统中放射性核素向安全壳及其辅助厂房的泄漏,计算了由此带来的气载放射性核素活度的变化。同时,对秦山二期核电厂常规运行工况下气载流出物释放源项进行了计算,并与设计值和实际测量值进行了比较分析。从结果来看,本文计算值比实测值和设计值约大一个量级,本文计算方法可为核电厂气载流出物释放源项提供一个上限值。
The production,transfer and release of the radionuclides within nuclear power reactor are analyzed in this article,also with the radionuclide concentration in primary coolant calculated.It also calculates the activity concentration inside the containment and the auxiliary buildings for the leakage of the primary coolant.The source term of airborne radioactive effluents at Qinshan NPP is calculated under the normal conditions.The calculated value is compared with designed value and measured value in the artic.As a result,the calculated value is an order magnitude higher than designed value and the measured value;it provides the upper limit value for the discharge of airborne radioactive effluents at NPPs.
出处
《辐射防护》
CAS
CSCD
北大核心
2010年第4期226-231,共6页
Radiation Protection
关键词
气载流出物
源项
常规运行工况
Airborne Radioactive Effluents
Source Terms
Normal Conditions
