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Safety analysis of reactivity initiated accidents in a HPLWR reactor by the coupled ATHLET-KIK03D code

机译:通过耦合的ATHLET-KIK03D代码对HPLWR反应堆中的反应性引发的事故进行安全性分析

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摘要

The dynamic core behavior of the HPLWR (High Performance Light Water Reactor) concept (Schulenberg, 2006), which is the European version of the GEN4 Supercritical Water Cooled Reactors (SCWR) was investigated in case of RIA (Reactivity Initiated Accidents) events. Before the analyses, the heat transfer correlations and property table of the supercritical water, built into the ATHLET code, were verified by using the Kirillov single channel thermal hydraulic measurements. According to the comparison of the calculations and the measurements, the Watt's correlation proved to be an appropriate one for average HPLWR conditions. The presented results of the performed analyses are reporting on significant perturbations of the power distribution. Furthermore, in comparison to PWRs, a more effective moderator feedback was obtained. The acceptance criteria are fulfilled, however, in spite of the relatively strong feedback, in some cases the hot channel temperatures are not far from the limits, which points out the importance of the RIA analyses. The observations can be explained by the sensitivity of the neutronic characteristics on the moderator density, changing in a wide range and, as a consequence, the significant perturbation of power peaking factors during the transients resulting in some cases larger local power increase than that originating from the average reactor power rise. © 2009 Elsevier Ltd. All riehts reserved.
机译:在发生RIA(反应性事故)事件的情况下,对欧洲版GEN4超临界水冷堆(SCWR)的HPLWR(高性能轻水堆)概念(Schulenberg,2006)的动态核心行为进行了研究。在分析之前,通过使用Kirillov单通道热工水力测量结果验证了内置在ATHLET代码中的超临界水的传热相关性和特性表。根据计算和测量结果的比较,瓦特相关性被证明是适用于平均HPLWR条件的一种相关性。所执行的分析的呈现结果报告了功率分布的显着扰动。此外,与PWR相比,获得了更有效的主持人反馈。但是,尽管有相对强烈的反馈,但仍满足了接受标准,在某些情况下,热通道温度离极限值并不远,这指出了RIA分析的重要性。这些观察结果可以通过中子特性对慢化剂密度的敏感度来解释,该变化在宽范围内变化,结果,在瞬态过程中功率峰值因子的显着扰动在某些情况下会导致局部功率增加的幅度大于源自反应堆平均功率上升。 ©2009 ElsevierLtd。保留所有权利。

著录项

  • 来源
    《Progress in Nuclear Energy》 |2010年第2期|p.190-196|共7页
  • 作者单位

    Hungarian Academy of Sciences KFK1 Atomic Energy Research Institute, H-1525 Budapest 114, POB 49, Hungary;

    Hungarian Academy of Sciences KFK1 Atomic Energy Research Institute, H-1525 Budapest 114, POB 49, Hungary;

    Hungarian Academy of Sciences KFK1 Atomic Energy Research Institute, H-1525 Budapest 114, POB 49, Hungary;

    Hungarian Academy of Sciences KFK1 Atomic Energy Research Institute, H-1525 Budapest 114, POB 49, Hungary;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    supercritical coolant reactivity initiated accident (ria) high performance light water reactor;

    机译:超临界冷却剂反应性引发事故(ria)高性能轻水堆;

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