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首页> 外文期刊>Annals of nuclear energy >Improvement of heat-removal capability using heat conduction on a novel reactor cavity cooling system (RCCS) design with passive safety features through radiation and natural convection
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Improvement of heat-removal capability using heat conduction on a novel reactor cavity cooling system (RCCS) design with passive safety features through radiation and natural convection

机译：通过在带有辐射和自然对流的被动安全功能的新型反应堆腔冷却系统（RCCS）设计上进行热传导来提高除热能力

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摘要

A previously-reported concept of reactor cavity cooling system (RCCS) with passive safety features consists of two continuous closed regions: an ex-reactor pressure vessel region and a cooling region with a heat-transfer surface to ambient air. The RCCS uses a novel shape to efficiently remove the heat released from the reactor pressure vessel (RPV) through thermal radiation and natural convection. Employing air as a working fluid and ambient air as an ultimate heat sink, the novel RCCS design strongly reduces the possibility of losing the heat sink for decay-heat-removal during nuclear accidents including a station blackout. The RCCS could stably and passively remove the heat released from the RPV and the decay heat after reactor shutdown. The previously-reported heat-removal rate of the RCCS was approximately 3 (kW/m2). The heat flux from the RPV surface of the High Temperature engineering Test Reactor (HTTR) is almost in the same range; 1.23–2.46 (kW/m2). In this paper, the authors address an improvement of heat-removal capability by considering potential of heat leakage due to heat conduction through the RCCS wall aimed at increasing a thermal reactor power level. Under the assumption of doubling the RCCS wall heat transfer area, a heat-flux removed by the RCCS could be doubled, such as approximately 6.2 (kW/m2).
机译：先前报告的具有被动安全功能的反应堆腔冷却系统（RCCS）的概念包括两个连续的封闭区域：反应堆前压力容器区域和带有向周围空气传热的冷却区域。 RCCS采用新颖的形状，可通过热辐射和自然对流有效地消除从反应堆压力容器（RPV）释放的热量。新颖的RCCS设计采用空气作为工作流体，并使用环境空气作为最终的散热器，从而极大地减少了在核电站事故（包括停电事故）期间因进行衰减散热而丢失散热器的可能性。 RCCS可以稳定和被动地去除RPV释放的热量和反应堆关闭后的衰减热量。先前报告的RCCS的散热速率约为3（kW / m2）。高温工程测试反应堆（HTTR）的RPV表面的热通量几乎在同一范围内； 1.23–2.46（kW / m2）。在本文中，作者考虑了由于通过RCCS壁进行热传导而导致的热泄漏潜能，目的是提高热反应堆的功率水平，从而提高了散热能力。在将RCCS壁传热面积增加一倍的假设下，RCCS去除的热通量可能会增加一倍，例如大约6.2（kW / m2）。

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  • 来源
    《Annals of nuclear energy》 |2018年第12期|201-206|共6页
  • 作者

    Kuniyoshi Takamatsu; Tatsuya Matsumoto; Wei Liu; Koji Morita;

  • 作者单位

    International Joint Research Group, HTGR Hydrogen and Heat Application Research Center, Japan Atomic Energy Agency;

    Department of Applied Quantum Physics and Nuclear Engineering Faculty of Engineering, Kyushu University;

    Department of Applied Quantum Physics and Nuclear Engineering Faculty of Engineering, Kyushu University;

    Department of Applied Quantum Physics and Nuclear Engineering Faculty of Engineering, Kyushu University;

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  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    RCCS; Passive safety; HTGR; Radiation; Natural convection; Heat conduction;

    机译：RCCS;被动安全;HTGR;辐射;自然对流;传热;

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