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Experimental and numerical analysis of dust resuspension for supporting chemical and radiological risk assessment in a nuclear fusion device

机译:用于核聚变设备化学和放射风险评估的粉尘悬浮的实验和数值分析

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摘要

A recognized safety issue for future fusion reactors fueled with deuterium and tritium is the generation of sizeable quantities of dust. Several mechanisms like plasma disruptions, Edge Localized Modes (ELM) and Vertical Displacement Events (VDE) resulting from material response to plasma bombardment in normal and off-normal conditions are responsible for generating dust of micron and sub-micron length scales inside the VV (Vacuum Vessel) of experimental fusion reactors like the International Thermonuclear Experimental Reactor (ITER). The loss of coolant accidents (LOCA), loss of coolant flow accidents (LOFA) and loss of vacuum accidents (LOVA) are types of accidents expected in experimental fusion reactors like ITER, which may jeopardize the components and the plasma vessel integrity and cause dust mobilization risk for workers and public. In particular the mobilization of the dust and its release outside the VV threatening public safety because it may contain tritium, may be radioactive from activation products, and may be chemically reactive and/or toxic. Understanding of the behavior of dust in an accident scenario will be essential in order to support the prevention and protection activities. A small facility, Small Tank for Aerosol Removal and DUST (STARDUST), was set up to perform experiments concerning the dust mobilization in a volume with the initial condition similar to those existing in ITER VV. The aim of this work was to reproduce a low pressurization rate (300 Pa/s) LOVA event in ITER due to a small air leakage, for two different positions of the leak (equatorial port level and at the divertor port level) in order to evaluate a first re-suspension numerical model by the analysis of the: 1. Influence of obstacles and temperature on dust resuspension during both maintenance and operative conditions; 2. The velocity field inside STARDUST. For the first experimental purpose the dusts used were tungsten (W), stainless steel (SS) and carbon (C), similar to those produced inside the vacuum chamber in a fusion reactor when the plasma facing materials vaporizes due to the high energy deposition. The experimental campaign has been carried out by introducing inside STARDUST facility an obstacle that simulates the presence of objects, like divertor and the limiter-divertor gap inside ITER VV. The walls of the tank are heated at two different temperatures, 25℃ 110℃ in order to reproduce the maintenance conditions and operative conditions. For the second experimental purpose, local measurements of velocity have been acquired by a capacitive transducer. A two-dimensional (2D) modelling of STARDUST has been set up by using a commercial CFD code (FLUENT), in order to get a preliminary overview of the fluid dynamics behavior during a LOVA event. The results of these simulations were compared against the experimental data for the CFD code validation. For validation purposes, the CFD simulation data were extracted at the same locations as the experimental data were collected. In this work, the computer-simulation data and the comparison with data collected during the laboratory studies will be presented and discussed.
机译:未来的以氘和tri为燃料的聚变反应堆公认的安全问题是产生大量的粉尘。在正常和非正常条件下,由材料对等离子轰击的材料响应导致的等离子破坏,边缘局限模式(ELM)和垂直位移事件(VDE)等几种机理可导致在VV内部产生微米级和亚微米级的灰尘(实验聚变反应堆(例如国际热核实验堆(ITER))的真空容器)。冷却剂事故(LOCA)的损失,冷却剂流动事故(LOFA)的损失和真空事故(LOVA)的损失是实验性聚变反应堆(如ITER)中预期发生的事故类型,可能会危害组件和等离子容器的完整性并引起粉尘工人和公众动员的风险。特别是灰尘的移动及其在VV外部的释放,威胁到公共安全,因为它可能含有t,可能从活化产物中放射出来,并且可能具有化学反应性和/或有毒。为了支持预防和保护活动,必须了解事故场景中粉尘的行为。建立了一个小型设施,用于除尘和除尘的小型储罐(STARDUST),以与初始条件与ITER VV中存在的条件类似的方式,进行了有关一定量的灰尘移动的实验。这项工作的目的是针对两个不同的泄漏位置(赤道口和分流器口),在空气中产生少量漏气,从而在ITER中产生低增压率(300 Pa / s)LOVA事件。通过分析以下内容评估第一重悬浮数值模型:1.在维护和操作条件下,障碍物和温度对重悬浮的影响; 2. STARDUST内部的速度场。出于第一个实验目的,使用的粉尘为钨(W),不锈钢(SS)和碳(C),与聚变反应堆中真空腔室内部产生的粉尘相似,当面对等离子体的材料由于高能沉积而蒸发时。通过在STARDUST设施内部引入一个障碍物来模拟实验活动,该障碍物可模拟物体的存在,例如ITER VV内部的偏滤器和限流器-偏滤器间隙。罐壁在两种不同的温度(25℃110℃)下加热,以重现维护条件和操作条件。为了第二个实验目的,已经通过电容传感器获取了速度的局部测量值。为了获得LOVA事件期间流体动力学行为的初步概况,已经使用商业CFD代码(FLUENT)建立了STARDUST的二维(2D)建模。将这些模拟的结果与用于CFD代码验证的实验数据进行了比较。为了验证,在与收集实验数据相同的位置提取了CFD模拟数据。在这项工作中,将介绍和讨论计算机模拟数据以及与实验室研究期间收集的数据的比较。

著录项

  • 来源
  • 会议地点 Tenerife(ES);Tenerife(ES)
  • 作者

    P.Gaudio; A.Malizia; I.Lupelli;

  • 作者单位

    University of Rome 'Tor Vergata', Faculty of Engineering, Department of Mechanical Engineering, Quantum Electronics and Plasma Physics Research Group, Via del Politecnico 1, 00133 Rome, Italy;

    University of Rome 'Tor Vergata', Faculty of Engineering, Department of Mechanical Engineering, Quantum Electronics and Plasma Physics Research Group, Via del Politecnico 1, 00133 Rome, Italy;

    University of Rome 'Tor Vergata', Faculty of Engineering, Department of Mechanical Engineering, Quantum Electronics and Plasma Physics Research Group, Via del Politecnico 1,00133 Rome, Italy;

  • 会议组织
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 系统科学;
  • 关键词

    dust mobilization; nuclear fusion safety; LOVA; CFD;

    机译:动员粉尘;核聚变安全;爱差价合约;

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