摘要
[目的]为了探索船用堆安全壳整体和局部泄漏率水平,明确安全壳密封性试验验收准则标准,并开展安全壳周围舱室的气载放射性物质浓度分析。[方法]基于陆上核电站安全壳密封性试验标准,根据"标准分析-提出指标-验证指标"的总体思路,开展浮动核电站泄漏率指标分配、泄漏率计算和可行性分析研究。[结果]结果表明,设计基准事故工况下,浮动核电站安全壳整体泄漏率应控制在3‰/24 h左右,B类和C类贯穿件泄漏率分配分别占整体泄漏率的10%和50%;在试验工况下,安全壳整体泄漏率考虑25%的设计余量。[结论]泄漏率数值分析计算结果满足指标要求,并具有较好的设计余量,对明确安全壳密封性试验验收准则具有重要参考价值。
[Objective]The purpose of this paper is to clarify the overall and local leakage rates of marine reactor safety vessel,establish the acceptance criteria of sealing test for reactor safety vessel and analyze the concentration of airborne radioactive material in surrounding cabins.[Methods]Based on the sealing test standard of land-based nuclear power plants,a study on index allocation and calculation of leakage rate as well as feasibility analysis of floating nuclear power plants(FNPP)are carried out in accordance with the general procedure of"standard analysis-indices proposing-indices verification".[Results]The results show that the proposed overall leakage rate of the reactor safety vessel of FNPP is about 3‰/24 h,and the leakage rate distribution of the penetrators of B&C types account for 10%and 50%of the overall leakage rate respectively under design basis accident conditions.During the sealing test,the overall leakage rate of the reactor safety vessel should be considered at 25%of the design margin.[Conclusion]The calculated leakage rate of FNPP meet the requirements of the index and the design margin is desirable,which is of great reference value for the establishment of containment sealing test acceptance criteria.
作者
季刚
苏晓亮
李海东
徐锋
谭美
JI Gang;SU Xiaoliang;LI Haidong;XU Feng;TAN Mei(Wuhan Second Ship Design and Research Institute,Wuhan 430205,China)
出处
《中国舰船研究》
CSCD
北大核心
2022年第1期141-146,共6页
Chinese Journal of Ship Research
基金
国家能源应用技术研究及示范工程资助项目(NY20150201)。
关键词
浮动核电站
安全壳
泄漏率
floating nuclear power plant
reactor safety vessel
leakage rate
