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首页> 外文期刊>Annals of nuclear energy >Experimental investigation of void distribution in suppression pool over the duration of a loss of coolant accident using steam-water two-phase mixture
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Experimental investigation of void distribution in suppression pool over the duration of a loss of coolant accident using steam-water two-phase mixture

机译:汽水两相混合物在失水事故期间抑制池中空隙分布的实验研究

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摘要

Studies are underway to determine if a large amount gas discharged through the downcomer pipes in the pressure suppression chamber during the blowdown of Loss of Coolant Accident (LOCA) can potentially be entrained into the Emergency Core Cooling System (ECCS) suction piping of BWR. This may result in degraded ECCS pumps performance which could affect the ability to maintain or recover the water inventory level in the Reactor Pressure Vessel (RPV) during a LOCA. Therefore, it is very important to understand the void behavior in the pressure suppression chamber during the blowdown period of a LOCA. To address this issue, a set of experiments is conducted using the Purdue University Multi-Dimensional Integral Test Assembly for ESBWR applications (PUMA-E) facility. The geometry of the test apparatus is determined based on the basic geometrical scaling analysis from a prototypical BWR containment (MARK Ⅰ) with a consideration of downcomer size, downcomer water submergence depth and Suppression Pool (SP) water level. Several instruments are installed in the test facility to measure the required experimental data such as the steam mass flow rate, void fraction, pressure and temperature. In the experiments, sequential flows of air, steam-air mixture and pure steam-each with the various flow rate conditions are injected from the Drywell (DW) through a downcomer pipe in the SP. Eight tests with two different downcomer sizes, various initial gas volumetric fluxes at the downcomer, and two different initial non-condensable gas concentration conditions in the DW are conducted. Three distinct phases, namely, an initial phase, a quasi-steady, and a chugging phase are observed. The maximum void penetration depth is observed in the initial phase. A reduction in the void penetration depth is observed in the quasi-steady phase. As a result of low non-condensable gas concentration, chugging is observed at the tail end of the experiment. Chugging provides renewed void penetrations comparable to those in the initial phase. It is determined that the void distribution and area of void penetration in the SP is governed by the gas volumetric flux at the downcomer and the non-condensable gas concentration in the downcomer.
机译:目前正在进行研究以确定在冷却水事故损失(LOCA)排污期间通过压力抑制室中的下降管排放的大量气体是否有可能被夹带到BWR的紧急堆芯冷却系统(ECCS)吸入管道中。这可能会导致ECCS泵性能下降,从而可能影响LOCA期间维持或恢复反应堆压力容器(RPV)中水存量的能力。因此,了解LOCA排污期间压力抑制腔中的空隙行为非常重要。为了解决此问题,使用普渡大学ESBWR应用程序多维集成测试组件(PUMA-E)进行了一组实验。测试设备的几何形状是根据原型BWR容器(MARKⅠ)的基本几何比例分析确定的,其中考虑了降液管尺寸,降液管水浸深度和抑制池(SP)水位。测试设备中安装了几台仪器,以测量所需的实验数据,例如蒸汽质量流量,空隙率,压力和温度。在实验中,空气,蒸汽-空气混合物和纯蒸汽(分别具有各种流速条件)的顺序流通过SP中的下降管从Drywell(DW)注入。进行了八项测试,其中使用了两种不同的降液管尺寸,降液管处的各种初始气体体积通量以及DW中的两种不同的初始不可冷凝气体浓度条件。观察到三个不同的阶段,即初始阶段,准稳态和颤动阶段。在初始阶段观察到最大的空隙渗透深度。在准稳态阶段观察到空隙渗透深度的减小。由于不凝性气体浓度低,在实验的尾端观察到了阻塞。充填可以提供与初始阶段相当的更新空隙渗透率。确定SP中的空隙分布和空隙渗透面积受降液管处的气体体积通量和降液管中不可凝气体浓度的控制。

著录项

  • 来源
    《Annals of nuclear energy》 |2015年第1期|570-580|共11页
  • 作者单位

    School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907-2017, USA,Department of Nuclear Engineering, Faculty of Engineering, Chulalongkorn University, Bangkok 10330, Thailand;

    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;

    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;

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

    Pressure suppression chamber; Suppression pool; Void distribution; Blowdown; LOCA;

    机译:压力抑制室;抑制池;空隙分布;排污;LOCA;

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