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Investigation on upper bounds of recriticality energetics of hypothetical core disruptive accidents in sodium cooled fast reactors

机译:钠冷快堆假想堆芯破坏性事故的临界性能学上限研究

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摘要

One key research goal for GEN-IV systems is an enhanced safety compared to the former Sodium Cooled Fast Reactor concepts. A key issue is built-in safety and the capability to prevent accidents and to demonstrate that their consequences do not violate aimed-at safety criteria. From the beginning of SFR development the Core Disruptive Accident (CDA) has played an outstanding role in the safety assessment. Under core disruptive accident conditions with core melting the fuel might compact, prompt criticality might be achieved and a severe nuclear power excursion with mechanical energy release might be the consequence. Numerous safety analyses accompanied the development and the licensing procedures of past fast reactor projects. A central issue of all analyses was the assessment of a realistic upper bound of energetics especially related to recriticalities in disrupted core configurations. Striving for an even higher safety level for next generation reactors a new strategy focused on the development and introduction of preventive and mitigative measures both to reduce the chance for a severe accident development and to mitigate its energetics. For assessing the effectiveness of these measures the knowledge of the CDA behavior is essential. In this context and on basis of new code developments, new experimental insights and extended studies for many reactor types of different power classes over the recent years, the issue of a realistic upper bound of energetics of the late core melt phases is again of relevance. Of special interest is the identification of natural and intrinsic mechanisms that limit the escalation of energetics. The current paper deals with these issues and tries to add supportive facts on the limits of CDA energetics. The evaluation of results of mechanistic SIMMER-II and SIMMER-III/IV analyses performed for various core designs and power classes and specific model case studies in 2D and 3D geometry indeed supports the idea of a limit of recriticality energetics. Intrinsic mechanisms exist, which limit the escalation energetics even in case of a strong blockage confinement suppressing any fuel discharge and allowing on-going sloshing recriticalities. In the light of the available information and taking into account relevant scientific publications and studies by the international community on the subject, one could conclude that an upper bound for energetics in the range given in the paper can be deduced.
机译:与以前的钠冷快堆概念相比,GEN-IV系统的一项主要研究目标是提高安全性。关键问题是内置的安全性以及预防事故并证明其后果不违反针对性安全标准的能力。从SFR的开发开始,核心破坏性事故(CDA)在安全评估中发挥了杰出的作用。在堆芯熔化的堆芯破坏性事故条件下,燃料可能会变紧,可能会迅速达到临界状态,并且可能导致伴随机械能释放的严重核电偏移。过去的快堆项目的开发和许可程序伴随着众多安全分析。所有分析的中心问题是评估能量学的实际上限,尤其是与破坏的核心配置中的重击性有关。为了进一步提高下一代反应堆的安全水平,新战略着重于制定和引入预防和缓解措施,以减少发生严重事故的机会并减轻其能量。为了评估这些措施的有效性,必须了解CDA行为。在这种情况下,并且根据近年来新的法规开发,新的实验见识和对不同功率类别的许多反应堆类型的扩展研究,关于后期堆芯熔体相的实际能量上限问题再次具有现实意义。特别令人感兴趣的是确定限制能量学升级的自然和内在机制。当前的论文处理这些问题,并试图在CDA能量学的局限性上增加支持性事实。对各种核心设计和功率等级进行的机械SIMMER-II和SIMMER-III / IV分析结果的评估,以及在2D和3D几何形状中的特定模型案例研究,确实支持了限制极限能量的想法。存在固有的机制,即使在强力的堵塞限制下抑制任何燃料排放并允许持续的晃动临界性,这种机制也限制了升级的能量。根据可获得的信息并考虑到国际社会有关该主题的相关科学出版物和研究,可以得出结论,可以推论出在本文给出的范围内能量学的上限。

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  • 来源
    《Nuclear Engineering and Design》 |2018年第1期|392-402|共11页
  • 作者单位

    KIT, Campus North,Hermann von Helmholtz Pl 1, D-76344 Eggenstein Leopoldshafen, Germany;

    KIT, Campus North,Hermann von Helmholtz Pl 1, D-76344 Eggenstein Leopoldshafen, Germany;

    KIT, Campus North,Hermann von Helmholtz Pl 1, D-76344 Eggenstein Leopoldshafen, Germany;

    KIT, Campus North,Hermann von Helmholtz Pl 1, D-76344 Eggenstein Leopoldshafen, Germany;

    Kyushu Univ, Dept Appl Quantum Phys & Nucl Engn, Nishi Ku, 744 Motooka, Fukuoka 8190395, 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
  • 中图分类
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