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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 >A REASSESSMENT OF LOW PROBABILITY CONTAINMENT FAILURE MODES
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A REASSESSMENT OF LOW PROBABILITY CONTAINMENT FAILURE MODES

机译：低概率保持故障模式的重新评估

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The recent events at Fukushima have highlighted the risks associated with beyond design basis accidents and the need for increased regulatory oversight of severe accident management. Even though the evidence is that the radiological health risk to humans is extremely small, in the future it is expected that there will be increased emphasis on preventing an unmitigated release of radioactivity to the environment with the potential for land contamination. Historically, risk assessments have given little credit for recovery actions but have also paid little attention to the impacts on severe accident progression of these actions. This work focuses on station blackout in large, dry pressurized water reactor (PWR) designs. The risk-dominant containment failure modes of NUREG-1150 are reassessed using the current state of knowledge for the severe accident phenomena that contribute to these failure modes. Some of the mechanisms that were considered as having the potential to result in containment failure at the time of NUREG-1150, such as in-vessel steam explosions and high pressure melt ejection, have subsequently undergone extensive review including additional experimentation and can be excluded from further consideration as viable failure modes for large, dry PWR containments. Other phenomena, such as combustible gas explosions, still require careful consideration when making severe accident management decisions. We have performed sensitivity studies using MELCOR to examine some of these phenomena. Particular attention has been paid to combustible gas generation, the effect of containment cooling on deflagration limits and the combustion load on containment within the context of possible mitigative actions. Combustion loads are compared to the NUREG-1150 containment fragility curve to assess the likelihood of containment failure.
机译：福岛最近发生的事件突出了与设计基准以外的事故有关的风险，以及需要加强对严重事故管理的监管力度。尽管有证据表明对人类的放射线健康风险极小，但在将来，人们仍希望将更多的重点放在防止放射线毫无缓释地释放到环境中而有可能污染土地。从历史上看，风险评估很少给予恢复行动以功劳，但也很少关注这些行动对严重事故进展的影响。这项工作的重点是大型干式压水堆（PWR）设计中的电站停电。使用当前的知识状态，重新评估NUREG-1150的风险主导型安全壳失效模式，以应对造成这些失效模式的严重事故现象。一些在NUREG-1150时代被认为有可能导致密闭失效的机制，例如船内蒸汽爆炸和高压熔体喷射，随后经过了广泛的审查，包括其他实验，可以从中排除。进一步考虑将其作为大型，干燥的压水堆安全壳的可行失效模式。在做出严格的事故管理决策时，仍然需要仔细考虑其他现象，例如可燃气体爆炸。我们已经使用MELCOR进行了敏感性研究，以研究其中一些现象。在可能采取的缓解措施的范围内，已经特别关注可燃气体的产生，安全壳冷却对爆燃极限的影响以及燃烧负荷对安全壳的影响。将燃烧负荷与NUREG-1150安全壳脆性曲线进行比较，以评估安全壳失效的可能性。

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