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首页> 外文会议>International meeting on severe accident assessment and management 2012: Lessons learned from fukushima dai-ichi >ANALYSIS OF ACCIDENT PROGRESSION OF FUKUSHIMA DAIICHI NPP WITH SAMPSON CODE - (1) UNIT 1
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ANALYSIS OF ACCIDENT PROGRESSION OF FUKUSHIMA DAIICHI NPP WITH SAMPSON CODE - (1) UNIT 1

机译：用Sampson规则分析福岛大地核电站的事故进展-（1）1号机组

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摘要

Accident progression of the unit-1 of Fukushima Daiichi nuclear power plants was analyzed with SAMPSON code. There were no decay heat removal systems available at the unit-1 except short term intermittent operation of the isolation condenser. The pressure transient in the reactor pressure vessel (RPV) was manually measured after the Tsunami: it was 7.0 MPa at 5 hours and 21 minutes after scram, and decreased to 0.9 MPa at 11 hours and 44 minutes after scram. RPV depressurization must occur at some time in the period of these two measurements. In the initial analysis, depressurization at 9 hours and 44 minutes after scram, when the drywell pressure measurement was 0.6 MPa, was assumed by opening the safety relief valve. The analysis results showed (1) that the RPV bottom failure occurred at 12 hours and 19 minutes after scram, and (2) that about 15.4 ton melt materials fell down into the drywell cavity at 14 hours and 22 minutes after scram. After that, it was clarified through detailed investigation of design specifications that the pressure boundary of the source range monitor (SRM) as one of the in-core monitors was inside the core. Therefore, direct release of reactor steam to the drywell might occur due to the SRM damage and this might be the cause of depressurization. Now, the SRM damage model is being incorporated in SAMPSON and then re-analysis is being performed.
机译：使用SAMPSON代码分析了福岛第一核电站1号机组的事故进展。除隔离冷凝器的短期间歇运行外，在单元1上没有可用的衰减除热系统。在海啸发生后，手动测量反应堆压力容器（RPV）中的瞬态压力：在填塞后5小时和21分钟时为7.0 MPa，在填塞后11小时和44分钟时降至0.9 MPa。 RPV降压必须在这两次测量期间的某个时间发生。在最初的分析中，通过打开安全泄压阀，假设干井压力测量为0.6 MPa时，在Scram之后9小时44分钟降压。分析结果表明：（1）RPV底部破裂发生在填塞后12小时和19分钟，（2）大约15.4吨熔融材料在填塞后14小时和22分钟掉入干井腔。此后，通过对设计规范的详细研究，我们弄清了作为核内监测器之一的源范围监测器（SRM）的压力边界位于岩心内部。因此，由于SRM损坏，可能会将反应堆蒸汽直接释放到干井中，这可能是降压的原因。现在，将SRM损坏模型合并到SAMPSON中，然后进行重新分析。

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