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Start-up transient test simulation with and without void-reactivity feedback for a two-phase natural circulation reactor

机译:两相自然循环反应器的有无反应性反馈的启动瞬态试验仿真

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摘要

The new small-scaled light water reactor design, known as integral modular water reactor (IMR), has an advantage compared to conventional light water reactor in terms of costs by adopting innovative technologies. However, this reactor may be susceptible to flow instabilities due to two-phase natural circulation inside the reactor pressure vessel (RPV). Flow instabilities may be amplified due to strong interaction between the flow and core power through the void-reactivity feedback mechanism. During the start-up of the IMR, system pressure is low. At low pressure, the density ratio can be quite high, which leads to large variation in void fraction due to change in flow quality. In the IMR design, the long riser and large volume of water can lead to thermal non-equilibrium between the phases due to the significant variation of the saturation temperature along flow direction. This can result in flow oscillations at certain operating conditions. In order to understand and identify the instability phenomena during the start-up of the reactor, a scaled experimental facility is designed based on the sound scaling approach. The scaling laws are used to obtain design parameters to maintain the similarities between prototype and experimental facility. Modified power scaling is used for transient tests. Four heater rods are used to simulate the chaotic flashing phenomena. In order to investigate the instability during the start-up procedure, start-up transient tests are performed with and without void-reactivity feedback for different core heat-up rate. These experimental results show that IMR is susceptible to instability during the start-up procedure at very low pressure. These oscillations are condensation induced oscillations and occur due to high subcooling in chimney section. It is investigated that, since amplitude of power oscillation is low, void-reactivity feedback effect does not affect the stability of the system for this type of given power transient.
机译:通过采用创新技术,新的小型轻水反应堆设计被称为整体模块化水反应堆(IMR),与常规轻水反应堆相比,在成本方面具有优势。但是,由于反应堆压力容器(RPV)内部的两相自然循环,该反应堆可能会受到流量不稳定的影响。由于通过孔隙反应性反馈机制的流动与堆芯功率之间的强相互作用,流动不稳定性可能会被放大。在IMR启动期间,系统压力较低。在低压下,密度比可能会很高,由于流动质量的变化,导致空隙率的大变化。在IMR设计中,由于饱和温度沿流动方向的显着变化,较长的立管和大量的水会导致各相之间的热不平衡。在某些操作条件下,这可能导致流动振荡。为了理解和识别反应堆启动过程中的不稳定性现象,基于声标度方法设计了按比例缩放的实验设施。缩放定律用于获取设计参数,以保持原型与实验设备之间的相似性。修改后的功率缩放用于瞬态测试。四个加热棒用于模拟混乱的闪烁现象。为了调查启动过程中的不稳定性,在有和没有空反应性反馈的情况下,针对不同的磁芯升温速率进行了启动瞬态测试。这些实验结果表明,IMR在非常低的压力下启动过程中很不稳定。这些振荡是凝结引起的振荡,是由于烟囱部分过冷造成的。研究表明,由于功率振荡的幅度低,对于这种给定的功率瞬变,空反应性反馈效应不会影响系统的稳定性。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2013年第12期|1131-1147|共17页
  • 作者单位

    School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907-2017, USA;

    School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907-2017, USA;

    School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907-2017, USA;

    Takasago Research and Development Center, Mitsubishi Heavy Industries, Ltd., 2-1-1 Shinhama Arai-Cho, Takasago, Hyogo 676-8686, Japan;

    Takasago Research and Development Center, Mitsubishi Heavy Industries, Ltd., 2-1-1 Shinhama Arai-Cho, Takasago, Hyogo 676-8686, Japan;

    Takasago Research and Development Center, Mitsubishi Heavy Industries, Ltd., 2-1-1 Shinhama Arai-Cho, Takasago, Hyogo 676-8686, 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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