...
  • 主题
高级搜索  >
历史搜索 清空历史
首页> 外文期刊>Annals of nuclear energy >Severe accident analysis of plant-specific spent fuel pool to support a SFP risk and accident management
【24h】

Severe accident analysis of plant-specific spent fuel pool to support a SFP risk and accident management

机译：对工厂专用乏燃料池进行严重事故分析，以支持SFP风险和事故管理

获取原文
获取原文并翻译 | 示例
   

获取外文期刊封面封底 >>

       
页面导航
  • 摘要
  • 著录项
  • 相似文献
  • 相关主题

摘要

The Fukushima accident that happened on March 11, 2011 has raised the possibility of severe accidents in an SFP under beyond design basis external events (BDBEEs) that might lead to a loss of all safety functions and need a way to cope effectively with such an event through a SFP risk and accident management. From a SFP safety point of view, the low decay heat of the fuel assemblies and large water inventory in an SFP may make the accident processes slow compared to an accident in the reactor core, but a huge number of fuel assemblies stored inside it and no containment in a SFP building (especially for PWR types) might be exposed to much greater risk. A quantitative analysis for SFP accidents can give more insights into which aspects play dominant roles in an accident progression. To date, however, few studies have been made for severe plant-level SFP accidents. This paper provides the plant-specific MELCOR analysis results for potential severe accidents that can be expected in a typical PWR. The SFP of the reference plant is located adjacent to the primary containment (outside primary containment), and its bottom is placed above the plant grade. Three representative accident scenarios (loss of cooling accident, loss of coolant inventory, and complete loss of coolant accident) and two different reactor operating modes (normal operation and refuelling mode) have been considered for the analysis. From the risk and accident management point of view, phenomenological analysis was mainly focused on (a) the level of the coolant, (b) the cladding temperature, (c) the mass of hydrogen generated during accident progressions, and (d) MCCI (Molten Cerium Concrete Interaction). (C) 2015 Elsevier Ltd. All rights reserved.
机译：2011年3月11日发生的福岛事故增加了SFP发生超出设计基准外部事件（BDBEE）的严重事故的可能性，这种事故可能导致所有安全功能丧失，需要一种有效应对此类事件的方法通过SFP风险和事故管理。从SFP安全的角度来看，与反应堆堆芯事故相比，SFP燃料组件的低衰减热量和大量积水可能会使事故过程变慢，但是内部堆放了大量燃料组件，没有SFP建筑物中的密闭性（尤其是对于PWR类型）可能面临更大的风险。 SFP事故的定量分析可以提供更多洞察力，以了解哪些方面在事故进展中起主要作用。但是，迄今为止，针对严重的工厂级SFP事故的研究很少。本文提供了针对特定PWR可能发生的潜在严重事故的特定于工厂的MELCOR分析结果。参考工厂的SFP位于主要安全壳附近（主要安全壳外），其底部位于植物等级上方。分析中考虑了三种有代表性的事故场景（冷却事故损失，冷却液存量损失和冷却液完全损失事故）和两种不同的反应堆运行模式（正常运行和加油模式）。从风险和事故管理的角度来看，现象学分析主要集中在（a）冷却液的液位，（b）包层温度，（c）事故进程中产生的氢气量和（d）MCCI（熔融铈混凝土相互作用）。 （C）2015 Elsevier Ltd.保留所有权利。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱：kefu@zhangqiaokeyan.com

京公网安备：11010802029741号 ICP备案号：京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有

  • 客服微信

  • 服务号