摘要
应用一体化严重事故分析MAAP5程序,建立三代非能动核电厂的安全壳模型,选取核电厂一回路主管道发生双端断裂叠加PRHR失效、IRWST重力注射失效作为始发事件,对事故进程、氢气源项、事故后惰化氢气缓解措施有效性和事故后惰化注入位置进行研究。结果表明:在整个事故过程中,堆芯锆合金与水反应产氢量累计为266kg,释放速率峰值可达0.55kg/s;事故后惰化CO_(2)注入氢气缓解措施可有效降低安全壳内氢气燃烧风险,且在1号SG源项隔间,源项隔间注入惰化气体CO_(2)比安全壳上部注入等量CO_(2)的效果更明显;在采取事故后惰化缓解安全壳内氢气风险时,我们必须考虑安全壳抽气系统防止安全壳超压威胁安全壳的完整性。
The integrated severe accident analysis MAAP5 program is applied to establish the containment model of the third generation passive nuclear power plant. Selecting the double end break superimposed PRHR failure and IRWST gravity injection failure of the the primary pipe as the initiating events, and the accident process, hydrogen source term, the effectiveness of post-inerting hydrogen mitigation measures and the post-inerting injection location are studied. The results show that the cumulative hydrogen production of zirconium alloy and water reaction is 266 kg, and the peak release rate is 0.55 kg/s during the whole accident;After the accident, the post-inerting mitigation measures of that CO_(2)injection into hydrogen can effectively reduce the risk of hydrogen combustion inside the containment, and the effect of inerting CO_(2)injection into the source compartment of 1# SG is more obvious than that of injecting the same amount of CO_(2)into the upper part of the containment. In order to mitigate the risk of hydrogen in the containment by post-inerting, we must consider the containment air extraction system to prevent overpressure from threatening the integrity of the containment.
作者
黄雄
魏巍
马国扬
谢明亮
冉晓隆
魏兴
HUANG Xiong;WEI Wei;MA Guoyang;XIE Mingliang;RAN Xiaolong;WEI Xing(China Nuclear Power Operation Technology Corporation,Wuhan of Hubei Prov.430223,China;FuJian FuQing Nuclear Power Co.Ltd.Fuqing of Fujian Prov.350318,China)
出处
《核科学与工程》
CAS
CSCD
北大核心
2022年第4期939-945,共7页
Nuclear Science and Engineering
