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Probabilistic safety analysis of an accelerator-Lithium target based experimental facility

机译:基于加速器-锂靶的实验设备的概率安全性分析

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摘要

The international fusion materials irradiation facility (IFMIF) is aimed to provide an intense neutron source by a high current deuteron linear accelerator and a high-speed lithium flow target, for testing candidate materials for future fusion reactors. An activity aimed at the safety assessment of the IFMIF plant as a whole has been carried out applying the probabilistic risk assessment (PRA) approach to identify and quantify in terms of expected frequencies, the dominant accident sequences related to the plant operation, and define the reference accident scenarios to be further analyzed through deterministic transient analysis, in order to verify the fulfilment of the safety criteria. The accident sequences have been modeled through the event tree technique, which allows identifying all possible combinations of success or failure of the safety systems in responding to a selection of initiating events. The identification of accident initiators, provided by the failure mode and effect analysis (FMEA) procedure, is followed by the systems analysis based on fault tree technique, for the unavailability assessment of the safety systems: finally the accident sequence scenarios are assessed by RISK SPECTRUM software. The study has allowed for the development of all accident sequences resulting from selected initiators relative to IFMIF plant and their grouping within sequence families, denoted as plant damage states, on account of the plant response and expected consequences. The frequency assigned to each family sequence is the sum of the contributors relative to all sequences ending into that particular plant state. The outcome of, the analysis shows that IFMIF plant is quite safe and presents no significant hazard to the environment: in fact all the sequences implying potential undesired effects as radioactive release to the outside, show very low frequencies, well below the limit for credible accident (1.0E-6/year). In addition, due to the novelty of the design and the large spreading assigned to the failure parameter probabilistic distributions (data utilized in the probabilistic analysis of this one of a kind plant are largely of a generic nature), an uncertainty analysis has been performed to add credit to the model quantification and to assess if the sequences have been correctly evaluated on the probability standpoint.
机译:国际聚变材料辐照设施(IFMIF)旨在通过高电流氘化线性加速器和高速锂流靶提供强中子源,以测试未来聚变反应堆的候选材料。已经应用概率风险评估(PRA)方法开展了一项旨在对IFMIF工厂整体进行安全评估的活动,以根据预期频率,与工厂运营相关的主要事故序列进行识别和量化,并确定通过确定性瞬态分析对参考事故场景进行进一步分析,以验证是否满足安全标准。事故序列已通过事件树技术进行了建模,该技术可识别安全系统在响应启动事件选择时的所有可能成功或失败组合。由故障模式和影响分析(FMEA)程序提供的事故引发者的识别,然后是基于故障树技术的系统分析,用于安全系统的不可用性评估:最后,由风险谱评估了事故序列场景软件。由于植物的反应和预期的后果,该研究已经允许开发出所有因IFMIF植物引发的事故序列,并将其归类到序列家族中的序列族(称为植物破坏状态)。分配给每个家族序列的频率是相对于所有终止于该特定植物状态的所有序列的贡献者之和。分析的结果表明,IFMIF工厂非常安全,对环境没有明显危害:实际上,所有暗示隐含着放射性释放到外部的潜在序列的序列都显示出非常低的频率,远低于可信事故的极限(1.0E-6 /年)。另外,由于设计的新颖性和分配给故障参数概率分布的较大分布(在对这种工厂的概率分析中使用的数据大部分是通用的),因此进行了不确定性分析在模型量化中增加功劳,并从概率角度评估序列是否已正确评估。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2006年第12期|p.1264-1274|共11页
  • 作者

    Luciano Burgazzi;

  • 作者单位

    ENEA-Centro Ricerche 'Ezio Clementel', Advanced Physics Technology Division, Via Martin di Monte Sole 4, 40129 Bologna, Italy;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
  • 关键词

  • 入库时间 2022-08-18 00:46:55

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