秦山一期核电站SGTR导致堆芯熔化进程及事故缓解措施的研究

Study on the Progression of Severe Core Damage Induced by SGTR and Mitigation Measures for QINSHAN NPP Unit 1

采用自行研制的核反应堆严重事故分析平台,对秦山-期核电站蒸汽发生器传热管破裂(SGTR)初因导致堆芯熔化严重事故进程进行了分析研究,并根据美国SANONOFRE核电站的IPE结果以及SURRY的PSA评估结果,选择适当的缓解措施,如一回路补给水、二回路补给水、一回路卸压等,对该事故做了相应的严重事故管理。通过计算分析,对阻止SGTR导致堆芯熔化进程的缓解措施的有效性进行了验证。

The progression of core damage induced by SGTR in Qinshan NPP Unit 1 is analyzed by a NPP severe accident simulator developed in this laboratory, based on SCDAP/RELAP5/ MOD3.1 and PROSYS. By employing the results of USA SAN ONOFRE NPP's IPE and SURRY's PSA, to end the core damage progression and mitigate the consequences of SGTR, the measures for the management of the severe accident induced by SGTR are selected, such as feed-and-bleed and depressurization, which are verified through the calculation by using the simulator. The results suggest that the implementing of feed-and-bleed and depressurization could be an available and effective way to arrest the SGTR sequences in Qinshan NPP Unit 1.