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首页> 外文期刊>Nuclear Engineering and Design >CFD simulations of moderator flow inside Calandria of the Passive Moderator Cooling System of an advanced reactor
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CFD simulations of moderator flow inside Calandria of the Passive Moderator Cooling System of an advanced reactor

机译：先进反应堆被动减速器冷却系统中减速器内部减速器流动的CFD模拟

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Passive systems are being examined for the future Advanced Nuclear Reactor designs. One of such concepts is the Passive Moderator Cooling System (PMCS), which is designed to remove heat from the moderator in the Calandria vessel passively in case of an extended Station Black Out condition. The heated heavy-water moderator (due to heat transferred from the Main Heat Transport System (MHTS) and thermalization of neutrons and gamma from radioactive decay of fuel) rises upward due to buoyancy, gets cooled down in a heat exchanger and returns back to Calandria, completing a natural circulation loop. The natural circulation should provide sufficient cooling to prevent the increase of moderator temperature and pressure beyond safe limits. In an earlier study, a full-scale 1D transient simulation was performed for the reactor including the MHTS and the PMCS, in the event of a station blackout scenario (Kumal 2013). The results indicate that the systems remain within the safe limits for 7 days. However, the flow inside a geometry like Calandria is quite complex due to its large size and inner complexities of dense fuel channel matrix, which was simplified as a 1D pipe flow in the aforesaid analysis. In the current work, CFD simulations are performed to study the temperature distributions and flow distribution of moderator inside the Calandria vessel using a three-dimensional CFD code, OpenFoam 2.2.0. First, a set of steady state simulation was carried out for a band of inlet mass flow rates, which gives the minimum mass flow rate required for removing the maximum heat load, by virtue of prediction of hot spots inside the Calandria. Next, a pseudo transient simulation was carried out by taking the power and mass flow rate at different time instants to the Calandria from the 1D analysis, as an input to the 3D steady state simulations. The results indicate that temperature hotspots are located at the top center of the fuel channel matrix depending on the operating regime. Furthermore, it was observed that for a period of 7 days the temperatures are well within the safe limits. (C) 2015 Elsevier B.V. All rights reserved.
机译：正在为未来的先进核反应堆设计检查无源系统。此类概念之一是被动减速器冷却系统（PMCS），该系统设计用于在长时间停电的情况下，从Calandria船中的减速器中被动散热。加热后的重水减速器（由于从主热传输系统（MHTS）传递的热量以及燃料放射性衰变引起的中子和伽马热化）由于浮力而上升，在热交换器中冷却并返回至Calandria ，完成自然循环。自然循环应提供足够的冷却，以防止调节剂温度和压力升高超过安全极限。在较早的研究中，在电站停电的情况下，对包括MHTS和PMCS在内的反应堆进行了全面的一维瞬态仿真（Kumal 2013）。结果表明，系统保持在安全限制范围内7天。然而，由于其大尺寸和密集的燃料通道矩阵的内部复杂性，像Calandria这样的几何形状内部的流相当复杂，在上述分析中简化为一维管道流。在当前的工作中，使用三维CFD代码OpenFoam 2.2.0进行CFD模拟以研究Calandria容器内部减速剂的温度分布和流量分布。首先，通过预测Calandria内部的热点，对一组入口质量流率进行了一组稳态仿真，这给出了消除最大热负荷所需的最小质量流率。接下来，通过将来自一维分析的到不同时间的功率和质量流率作为一维3D稳态仿真的输入，来进行伪瞬态仿真。结果表明，温度热点取决于运行方式位于燃料通道矩阵的顶部中心。此外，观察到在7天的时间内温度完全在安全范围内。 （C）2015 Elsevier B.V.保留所有权利。

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  • 来源
    《Nuclear Engineering and Design》 |2015年第10期|193-203|共11页
  • 作者

    Pal Eshita; Kumar Mukesh; Joshi Jyeshtharaj B.; Nayak Arun K.; Vijayan Pallippattu K.;

  • 作者单位

    Homi Bhabha Natl Inst, Mumbai 400094, Maharashtra, India;

    Bhabha Atom Res Ctr, Reactor Engn Div, Mumbai 400085, Maharashtra, India|Inst Chem Technol, Dept Chem Engn, Mumbai 400019, Maharashtra, India;

    Homi Bhabha Natl Inst, Mumbai 400094, Maharashtra, India;

    Bhabha Atom Res Ctr, Reactor Engn Div, Mumbai 400085, Maharashtra, India;

    Bhabha Atom Res Ctr, Reactor Engn Div, Mumbai 400085, Maharashtra, India;

  • 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);
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