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Development of technical basis in the initiating and transition phases of unprotected events for Level-2 PSA methodology in sodium-cooled fast reactors

机译:为钠冷快堆中2级PSA方法的未保护事件的引发和过渡阶段开发技术基础

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摘要

A probabilistic safety assessment (Level-2 PSA) methodology was developed tor comprehensive risk evaluation of sodium-cooled fast reactors. As part of this development, in this paper, phenomenological event trees were developed as well as technical database to quantify the probability of event sequences in the Level-2 PSA, focusing on the initiating and transition phases of unprotected events. Typical and important accident categories were selected: unprotected loss of flow (ULOF), unprotected transient overpower (UTOP) and unprotected loss of heat sink (ULOHS). Based on the state-of-the-art knowledge, the headings of these event trees were selected so that dominant factors in accident consequences can be represented appropriately. For each of the headings, available information for the probability quantification were reviewed and integrated as the technical database for the Level-2 PSA. It was clarified that the headings of the ULOF category, for which experimental database and evaluation models have been reasonably established, can be commonly applied to certain part of the different accident categories except for some specific points, which were identified in this study. For the ULOHS category, an additional event tree is necessary before the core disruption providing various boundary conditions for the initiating phase. For the transition phase, dominant factors were also identified through parametric analyses. In the Japan sodium-cooled fast reactor, an inner duct is introduced into a fuel subassembly for enhancing molten fuel discharge from disrupted core in the transition phase. The parametric study showed that the analytical case without the fuel discharge through the inner duct resulted in an occurrence of recriticality regardless of the fuel discharge through control-rod guide tubes. This suggests that the fuel discharge through the inner duct is essential to avoid severe recriticality in the transition phase.
机译:针对钠冷快堆的综合风险评估,开发了概率安全评估(2级PSA)方法。作为此发展的一部分,本文开发了现象学事件树以及技术数据库来量化Level-2 PSA中事件序列的概率,重点是未受保护事件的启动和过渡阶段。选择了典型和重要的事故类别:无保护的流量损失(ULOF),无保护的瞬态过功率(UTOP)和无保护的散热片(ULOHS)。基于最新知识,选择了这些事件树的标题,以便可以恰当地表示事故后果中的主要因素。对于每个标题,都对概率量化的可用信息进行了审核,并整合为Level 2 PSA的技术数据库。明确指出,已经合理建立了实验数据库和评估模型的ULOF类别的标题通常可以应用于不同事故类别的某些部分,但本研究中已确定了某些特定要点。对于ULOHS类别,在核心中断之前为启动阶段提供各种边界条件之前,需要一个附加的事件树。对于过渡阶段,还可以通过参数分析确定主导因素。在日本的钠冷快堆中,内部管道被引入燃料组件中,以增强过渡阶段从破裂的堆芯中排出熔融燃料的能力。参数研究表明,没有通过内部导管排放燃油的分析情况导致了重新临界的发生,而与通过控制杆导管排放的燃油无关。这表明通过内管排出的燃料对于避免过渡阶段出现严重的重临界至关重要。

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  • 来源
    《Nuclear Engineering and Design》 |2012年第8期|p.212-227|共16页
  • 作者单位

    Japan Atomic Energy Agency, 4002 Narita-cho, O-arai, Ibaraki 311-1393, Japan;

    Japan Atomic Energy Agency, 4002 Narita-cho, O-arai, Ibaraki 311-1393, Japan;

    Japan Atomic Energy Agency, 4002 Narita-cho, O-arai, Ibaraki 311-1393, Japan;

  • 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
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