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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 >Investigation on Thermal-hydraulics and Core Degradation Issues of Fukushima Accident by relap5-scdap code
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Investigation on Thermal-hydraulics and Core Degradation Issues of Fukushima Accident by relap5-scdap code

机译：用relap5-scdap代码调查福岛事故的热工水力和岩心降解问题

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This paper presents the analysis of the accident occurred at Fukushima Unit-3 Nuclear Power Plant, taking into account the latest and more detailed description of the events available. To this aim, the accidental sequence has been simulated by RELAP5/SCDAP code. The analysis is focused on the phenomenology that had a predominant role into the accident evolution at Unit 3. The RELAP5/SCDAP 3.5da version is used on the basis of the Laguna Verde BWR plant nodalization made available by Innovative Systems Software (ISS) Group, chaired by Prof. Allison. The nodalization has been modified with respect to the main systems in service during the sequence. The modifications to the nodalization have been performed also for reducing the error mass in the calculation of the very long thermal-hydraulic transients, like that occurred at Fukushima Unit 3. The good results obtained also for this phase of the accident, which lasted about 2 days, will be presented. However, the most interesting part of the analysis is obviously that of core damage. The coupling of RELAP5 with SCDAP models allows simulating the core degradation progression and the hydrogen production, starting from the condition of "core isolation phase", until resumption of the coolant level through Fire Extinguishing Line was actuated. The calculation results are discussed on the basis of the available plant data, even though incomplete. In fact, the real state of core degradation remains unknown and requires direct investigations in situ. Only once a reactor examination program will be harried out, an extensive and comprehensive data base will be available on the phenomena occurred during the core melt scenario progression, including aspects related to material relocation processes inside the vessel and consequent radioactivity releases. However, it is already possible to evaluate the influence of some uncertain core degradation parameters on core melt progression, like fuel rod slumping criteria with associated heat transfer phenomena. Some considerations on the lessons learned from the Fukushima accident conclude the paper.
机译：本文介绍了对福岛3号核电站发生的事故的分析，同时考虑了对现有事件的最新和更详细的描述。为此，已通过RELAP5 / SCDAP代码对意外序列进行了模拟。分析的重点是在3号机组事故演变中起主要作用的现象学。RELAP5/ SCDAP 3.5da版本是根据Innovative Systems Software（ISS）集团提供的Laguna Verde BWR工厂节点化技术使用的，由艾里森教授主持。在此序列中，已针对服务中的主要系统对节点进行了修改。还对节点进行了修改，以减少计算非常长的热工水力瞬变时的误差质量，就像在福岛3号机组中发生的那样。事故的这一阶段也取得了良好的结果，历时约2年。天，将被介绍。但是，分析中最有趣的部分显然是核心损坏。 RELAP5与SCDAP模型的耦合允许从“岩心隔离阶段”的条件开始模拟岩心的降解进程和氢的产生，直到通过灭火管路恢复冷却液的液位。即使不完整，也会根据可用的工厂数据讨论计算结果。实际上，核心退化的真实状态仍然未知，需要现场直接调查。只有一旦执行了反应堆检查程序，才能获得有关堆芯融化过程进展期间发生的现象的广泛而全面的数据库，包括与容器内材料重新定位过程有关的方面以及随之而来的放射性释放。但是，已经有可能评估一些不确定的堆芯退化参数对堆芯融化进展的影响，例如带有相关传热现象的燃料棒塌落准则。本文总结了从福岛事故中汲取的经验教训。

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