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Experimental study of void behavior in a suppression pool of a boiling water reactor during the blowdown period of a loss of coolant accident.

机译:冷却剂损失事故排污期间沸水反应堆抑制池中空隙行为的实验研究。

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摘要

The possible failure of an Emergency Core Cooling System (ECCS) train due to a large amount of entrained gas in the ECCS pump suction piping in a Loss of Coolant Accident (LOCA) is one of the potential engineering problems faced in a Boiling Water Reactor (BWR) power plant. To analyze potential gas intrusion into the ECCS pump suction piping, the study of void behavior in the Suppression Pool (SP) during the LOCA is necessary. The void fraction distribution and void penetration are considered as the key parameters in the problem analysis. Two sets of experiments, namely, steady-state tests and transient tests were conducted using the Purdue University Multi-Dimensional Integral Test Assembly for ESBWR application (PUMA-E) to study void behavior in the SP during the blowdown. The design of the test apparatus used is based on the scaling analysis from a prototypical BWR containment (MARK-I) with consideration of the downcomer size, the SP water level, and the downcomer water submergence depth. Several instruments were installed to obtain the required experimental data, such as inlet gas volumetric flow, void fraction, pressure, and temperature.;For the steady-state tests, the air was injected through a downcomer pipe in the SP in order to simulate the physical phenomena in the SP during the initial blowdown of LOCA. Thirty tests were performed with two different downcomer sizes (0.076 and 0.102 m), various air volumetric flow rates or flux (0.003 to 0.153 m3/s or 0.5 to 24.7 m/s), initial downcomer void conditions (fully filled with water, partially void, and completely void) and air velocity ramp rates (one to two seconds). Two phases of the experiment were observed, namely, the initial phase and the quasi-steady phase. The initial phase produced the maximum void penetration depth; and the quasi-steady phase showed less void penetration with oscillation in the void penetration. The air volumetric flow rate was found to have a minor effect on the void fraction distribution and void penetration during the initial phase, which was in the range of high air volumetric flow rate conditions; however, it strongly impacted the void fraction distribution and void penetration during the quasi-steady phase for the entire ranges of air volumetric flow rate conditions. The initial downcomer void conditions were found to strongly affect the void fraction distribution and void penetration during the initial phase. The air velocity ramp rates were found to have a minor impact on void distribution and penetration in both phases. The downcomer cross-sectional areas did not significantly impact the average void penetration (both axial and radial) for those tests having comparable initial air volumetric flux.;For the transient tests, sequential flows of air, steam-air mixtures, and pure steam, with the various flow rate conditions, were injected from the Drywell (DW) through a downcomer pipe in the SP. Eight tests were conducted with two different downcomer sizes (0.076 and 0.102 m), various gas volumetric flux levels (17 to 84 m/s) at the downcomer, and two different initial air concentration conditions in the DW (80% and 100% of air concentration). Three phases of experiments, (i.e., initial phase, quasi-steady phase, and chugging phase) were observed. The void penetration depth was at the maximum level in the initial phase and at a reduced level in the quasi-steady phase. The chugging that occurred at the tail end of the experiment provided renewed void penetrations that were comparable to those in the initial phase. It was determined that the void fraction distribution and the void penetration in the SP were governed by the gas volumetric flux at the downcomer and by the air concentration in the downcomer. The downcomer cross-sectional areas did not significantly impact the average void penetration (both axial and radial) for those tests having comparable initial gas volumetric flux.
机译:沸水反应堆(沸腾堆)面临的潜在工程问题之一是,由于冷却水事故(LOCA)中ECCS泵吸入管道中夹带大量气体,紧急情况核心冷却系统(ECCS)列车可能发生故障。 BWR)发电厂。为了分析潜在气体侵入ECCS泵吸入管道的情况,有必要研究LOCA期间抑制池(SP)中的空隙行为。空隙率分布和空隙渗透被认为是问题分析中的关键参数。使用普渡大学ESBWR应用多维整体测试组件(PUMA-E)进行了两组实验,即稳态测试和瞬态测试,以研究排污期间SP中的空隙行为。所使用的测试设备的设计基于对原型BWR容器(MARK-I)的比例分析,并考虑了下降管尺寸,SP水位和下降管水浸深度。安装了几台仪器以获取所需的实验数据,例如进气体积流量,空隙率,压力和温度。对于稳态测试,通过SP中的下降管注入空气,以模拟空气流动。 LOCA初始排污期间SP中的物理现象。在两种不同的降液管尺寸(0.076和0.102 m),各种空气体积流量或通量(0.003至0.153 m3 / s或0.5至24.7 m / s),初始降液管空隙条件(完全充满水,部分充满水)下进行了30次测试无效,并且完全无效)和风速上升速率(一到两秒)。观察到实验的两个阶段,即初始阶段和准稳态阶段。初始阶段产生了最大的孔隙渗透深度。准稳态相显示出较少的空洞穿透,且空洞穿透发生了振荡。发现在初始阶段,空气体积流量对空隙分数分布和空隙渗透影响较小,这在高空气体积流量条件下是有效的。然而,在整个空气体积流量条件范围内,它在准稳态阶段严重影响了空隙率分布和空隙渗透。发现初始降液管空隙条件在初始阶段强烈影响空隙分数分布和空隙渗透。发现空气速度的上升速率对两相中的空隙分布和渗透都具有较小的影响。对于具有可比初始空气体积通量的那些测试,降液管的横截面面积没有显着影响平均空隙渗透(轴向和径向);对于瞬态测试,空气,蒸汽-空气混合物和纯蒸汽的顺序流动,在各种流速条件下,通过SP中的下导管从Drywell(DW)注入。进行了八项测试,其中有两种不同的降液管尺寸(0.076和0.102 m),降液管处的各种气体体积通量水平(17至84 m / s)以及DW中的两种不同的初始空气浓度条件(80%和100%的DW)。空气浓度)。观察到实验的三个阶段(即初始阶段,准稳定阶段和颤动阶段)。空隙渗透深度在初始阶段处于最大水平,而在准稳态阶段则处于减小的水平。在实验的尾部发生的发声提供了与初始阶段相当的更新的空隙渗透率。已确定SP中的空隙率分布和空隙渗透率受降液管处的气体体积通量和降液管中空气浓度的支配。对于具有可比初始气体体积通量的那些测试,降液管横截面面积没有显着影响平均空隙渗透(轴向和径向)。

著录项

  • 作者

    Rassame, Somboon.;

  • 作者单位

    Purdue University.;

  • 授予单位 Purdue University.;
  • 学科 Engineering General.;Engineering Nuclear.
  • 学位 Ph.D.
  • 年度 2012
  • 页码 203 p.
  • 总页数 203
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

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