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Severe accident studies on the efficiency of mitigation devices in a SFR core with SIMMER code

机译:Simmer Code的SFR核心中减缓装置效率的严重事故研究

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摘要

Sodium-cooled Fast Reactors (SFR) are investigated as future Generation IV reactor concepts. In SFR, the core configuration is not the most reactive during the nominal reactor operation, its geometry change or coolant voiding can induce a reactivity insertion. Within these considerations, mitigation devices should be implemented into the core in order to limit the thermal energy released into the fuel during a severe accident and thereby the possibility to induce mechanical loadings of the reactor structure when vaporized materials expand. Complementary safety devices called Transfer Tubes (TT) are studied in a French concept as an effective mitigation measure of severe accidents to reach a final reactor safe state, even in case of a failure of all shutdown systems including the passive shutdown safety rods. More precisely the TT, with their upper part located in and above the core, cross the core support structure and are linked to the core catcher zone situated in the main vessel bottom. Their purpose is to extract fissile materials from the core zone and secondly to favor the transfer of the molten fuel from the core region to the core catcher in case of severe core damage. The fuel discharge out of the core zone is necessary in order to lower the core reactivity, the relocation into the core catcher is necessary to enable the stabilization, the sub-criticality and the fuel cooling. An extensive work on severe accident calculations and phenomena identification related to fuel discharge through TT was performed. These studies represent the outcome of the work performed in 2014-2019, performed with collaboration of Japanese JAEA and MFBR and Framatome in the framework of the SFR project carried out by CEA. Calculations of fuel discharge were carried out with the mechanistic calculation code SIMMER and the main results are presented in this paper. Firstly, the whole unprotected loss of flow (ULOF) accident sequence was calculated with the SIMMER code. From these calculations, the power and flow evolution were set as boundary conditions for a more detailed model with six fuel assemblies around TT. This model was used to focus on key phenomena and to check impact of design parameter as local bottom restriction inside TT on fuel discharge way.
机译:钠冷却的快速反应器(SFR)被调查为未来一代IV反应堆概念。在SFR中,核心配置在标称反应器操作期间不是最具反应性的,其几何变化或冷却剂空隙可以引起反应性插入。在这些考虑中,缓解装置应该被实施到核心中,以限制在严重事故中释放到燃料中的热能,从而在汽化材料膨胀时可能诱导反应器结构的机械负载。在法国概念中研究了称为转移管(TT)的互补安全装置,作为严重事故的有效缓解措施,以达到最终反应堆安全状态,即使在包括被动关闭安全杆的所有关闭系统的情况下。更确切地说是TT,它们的上部位于芯中和上方,穿过芯支撑结构并与位于主容器底部的核心捕集区连接。他们的目的是从芯区中提取裂变材料,其次是为了有利于在严重核心损伤的情况下将熔融燃料从芯区域转移到芯捕机。为了降低核心反应性,需要燃料排出核心区,以使芯捕机进入芯捕机以使稳定,亚临界性和燃料冷却所必需的。进行了通过TT的燃料放电相关的严重事故计算和现象识别的广泛工作。这些研究代表了2014 - 2019年在CEA开展的SFR项目的框架中进行了日本JAEA和MFBR和MFBR和Framatome进行的工作的结果。用机械计算代码进行燃烧燃料放电的计算,并在本文中提出了主要结果。首先,用煨代码计算整个未受保护的流动丢失(ULOF)事故序列。从这些计算,电力和流动演化被设定为具有围绕TT周围的六个燃料组件的更详细模型的边界条件。该模型用于专注于关键现象,并检查设计参数的影响在燃料放电方面TT内部的局部底部限制。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2021年第3期|111037.1-111037.12|共12页
  • 作者单位

    IRESNE Commissariat Energie Atom & Energies Alternat CEA DER F-13108 St Paul Les Durance France;

    IRESNE Commissariat Energie Atom & Energies Alternat CEA DER F-13108 St Paul Les Durance France;

    IRESNE Commissariat Energie Atom & Energies Alternat CEA DER F-13108 St Paul Les Durance France;

    IRESNE Commissariat Energie Atom & Energies Alternat CEA DER F-13108 St Paul Les Durance France;

    JAEA 4002 Narita Oarai Ibaraki 3111393 Japan;

    JAEA 4002 Narita Oarai Ibaraki 3111393 Japan;

    JAEA 4002 Narita Oarai Ibaraki 3111393 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
  • 关键词

    Severe accident mitigation; Molten core material discharge; SIMMER code; Sodium-cooled Fast Reactors (SFRs);

    机译:严重的事故缓解;熔融芯材料放电;煨代码;钠冷却的快电抗器(SFR);
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