首页> 外文会议>UIT Heat Transfer Conference >Two-Phase flow instrumentation for nuclear accidents simulation
【24h】

Two-Phase flow instrumentation for nuclear accidents simulation

机译:核事故模拟的两相流量仪表

获取原文

摘要

The paper presents the research work performed at the Energy Department of the Politecnico di Torino, concerning the development of two-phase flow instrumentation and of models, based on the analysis of experimental data, that are able to interpret the measurement signals. The study has been performed with particular reference to the design of power plants, such as nuclear water reactors, where the two-phase flow thermal fluid dynamics must be accurately modeled and predicted. In two-phase flow typically a set of different measurement instruments (Spool Piece - SP) must be installed in order to evaluate the mass flow rate of the phases in a large range of flow conditions (flow patterns, pressures and temperatures); moreover, an interpretative model of the SP need to be developed and experimentally verified. The investigated meters are: Turbine, Venturi, Impedance Probes, Concave sensors, Wire mesh sensor, Electrical Capacitance Probe. Different instrument combinations have been tested, and the performance of each one has been analyzed.
机译:本文提出了在PoliteCnico diorino的能量部门进行的研究工作,基于对实验数据的分析,可以解释测量信号的两相流动仪表和模型的开发。该研究已经特别参考发电厂的设计,例如核水反应器,其中两相流体热流体动力学必须准确地建模和预测。在两相流中,通常必须安装一组不同的测量仪器(阀芯件 - SP),以便在大范围的流动条件下评估相的质量流量(流动图案,压力和温度);此外,需要开发和实验验证SP的解释模型。调查仪表是:涡轮机,文丘里,阻抗探针,凹形传感器,电气电容探头。已经测试了不同的仪器组合,并分析了每个仪器组合。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号