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EPRI MAAP5 FUKUSHIMA DAIICHI ANALYSIS

机译:把p5 p5 fukushima放了它很好。

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摘要

The study presented in this paper summarizes work conducted as part of the EPRI Fukushima Technical Evaluation project. This effort is designed to develop a representation of the core damage events that occurred at Fukushima Daiichi Units 1, 2 and 3 during March 2011 using the analytical capabilities provided by the EPRI Modular Accident Analysis Program, Version 5 (MAAP5). The analytical investigations of Fukushima Daiichi performed with MA AP5 indicate that core melt progressions at Units 1, 2 and 3 likely span a range of core damage conditions. The core status at Unit 1 is likely consistent with a large fraction of core debris having relocated into the containment. By contrast, the MAAP5 evaluations indicate that there is a reasonable potential for a significant fraction of core debris to be retained inside the RPV at Unit 2. The corresponding Unit 3 simulations, however, highlight the important role that degraded HPCI operation at low RPV pressure may have played in promoting some relocation of core debris out of the RPV and into containment. The detailed containment evaluations conducted as part of this study also highlight the critical role played by thermal stratification phenomena (either in the suppression pool or in the drywell) in influencing the magnitude of containment pressure and thermal challenges. These simulations highlight the potentially critical role that thermal stratification in the upper drywell may have played in accelerating the onset of leakage through the drywell head flange due to thermal degradation of the drywell head gasket. Finally, these simulations of reactor and containment response provide good representations of the occurrence of flammable conditions in the Units 1 and 3 reactor buildings, supporting the nature and timing of the observed reactor building combustion events.
机译:本文提出的这项研究总结了作为EPRI福岛技术评估项目的一部分进行的工作。这项努力旨在使用EPRI模块化事故分析计划第5版(MAAP5)提供的分析能力,制定福岛达奇单位1,2和3所发生的核心损坏事件的代表。用MA AP5进行的Fukushima Daiichi的分析研究表明,单位1,2和3的核心熔体进展可能跨越一系列核心损伤条件。单元1的核心状态可能与大部分核心碎片迁移到容纳中一致。相比之下,MAAP5评估表明,在单元2的情况下,有显着的核心碎片存在核心碎片的显着潜力。然而,相应的单元3模拟突出显示在低RPV压力下降低HPCI操作的重要作用可能已经在促进RPV中的一些核心碎片搬迁并进入遏制。作为这项研究的一部分而进行的详细评估围堵也突出了影响壳压力和热挑战的幅度由热分层现象(无论是在抑制池或干井)发挥的关键作用。这些模拟突出了上层干燥中的热分层可能已经在通过干燥头垫圈的热劣化而在通过干燥的头部凸缘的泄漏开始的潜在关键作用。最后,这些反应器和容纳响应的模拟提供了单位1和3个反应器建筑物中易燃条件的良好表示,支持观察到的反应器建筑物燃烧事件的性质和定时。

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