大破口触发的严重事故分析及缓解措施研究
发布时间：2018-08-01 15:48
【摘要】：采用严重事故一体化分析程序MELCOR,对国产先进压水堆核电厂进行系统建模,选取大破口触发的严重事故进行校核计算研究,获得了严重事故工况下核电厂关键参数的瞬态特性和非能动系统响应特性,并与安全分析报告中MAAP的计算结果进行了对比分析。结果表明:虽然校核计算结果与安全分析报告中的结果存在一定差异,但总体上事故序列和主要参数的变化趋势吻合良好,并且都能够在严重事故情况下保持压力容器和安全壳的完整性,放射性裂变产物释放量极低,缓解措施的设计能够有效缓解事故进程,满足核电厂的安全要求。
[Abstract]:The system model of domestic advanced pressurized water reactor (PWR) nuclear power plant is established by using the integrated analysis program MELCOR, and the serious accident triggered by a large break is selected to be checked and calculated. The transient characteristics of the key parameters and the response characteristics of the inactive system are obtained under the severe accident conditions. The results are compared with the MAAP calculation results in the safety analysis report. The results show that although there are some differences between the calculation results and the results in the safety analysis report, the variation trend of the accident sequence and the main parameters is in good agreement on the whole. Both of them can maintain the integrity of pressure vessels and containment in serious accidents, and the release of radioactive fission products is very low. The design of mitigation measures can effectively alleviate the accident process and meet the safety requirements of nuclear power plants.
【作者单位】： 环境保护部核与辐射安全中心;
【基金】：大型先进压水堆及高温气冷堆电站国家科技重大专项:CAP1400安全审评关键技术研究(2013ZX06002001)
【分类号】：TL364.4;TM623
本文编号：2158063
[Abstract]:The system model of domestic advanced pressurized water reactor (PWR) nuclear power plant is established by using the integrated analysis program MELCOR, and the serious accident triggered by a large break is selected to be checked and calculated. The transient characteristics of the key parameters and the response characteristics of the inactive system are obtained under the severe accident conditions. The results are compared with the MAAP calculation results in the safety analysis report. The results show that although there are some differences between the calculation results and the results in the safety analysis report, the variation trend of the accident sequence and the main parameters is in good agreement on the whole. Both of them can maintain the integrity of pressure vessels and containment in serious accidents, and the release of radioactive fission products is very low. The design of mitigation measures can effectively alleviate the accident process and meet the safety requirements of nuclear power plants.
【作者单位】： 环境保护部核与辐射安全中心;
【基金】：大型先进压水堆及高温气冷堆电站国家科技重大专项:CAP1400安全审评关键技术研究(2013ZX06002001)
【分类号】：TL364.4;TM623
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