节点文献
螺旋管式直流蒸汽发生器热工水力分析模型
Thermal-hydraulic Model for Helical-coil Once-through Steam Generator
【Author】 YUAN Yuan;PENG Min-jun;XIA Geng-lei;LV Xing;Fundamental Science on Nuclear Safety and Simulation Technology Laboratory,Harbin Engineering University;
【机构】 哈尔滨工程大学核安全与仿真技术国防重点学科实验室;
【摘要】 基于混合流模型的质量、动量和能量守恒方程,采用可移动边界法建立了压水堆螺旋管式直流蒸汽发生器的稳态和动态分析模型。模型将二次侧传热区域分为预热段、蒸发段和过热段,且考虑了缺液区传热。通过对国际革新与安全反应堆(IRIS)螺旋管式直流蒸汽发生器的模拟,对模型进行了验证。结果表明,本文所建立的稳态和动态模型合理,稳态计算结果与设计值符合良好,动态仿真符合热工水力学及其定性机理分析结果。
【Abstract】 Based on the conservation equations of fluid mass,momentum and energy,a thermal-hydraulic model for helical-coil tube type once-through steam generator(HCSG)was developed by movable boundary method.The heat transfer control volume was divided into three segments:economizer,evaporator and superheater regions,and the mist evaporation region was taken into account.The thermal-hydraulic model was evaluated against the data of the HCSG of the International Reactor Innovative and Secure(IRIS).The steady state results of the new model are in good agreement with the design parameters of IRIS,and the dynamic simulation results are suitable for the thermal-hydraulic analysis of HCSG.
【Key words】 helical-coil once-through steam generator; mixed flow model; moving boundary method; thermal-hydraulic model;
- 【会议录名称】 北京核学会第十届(2014年)核应用技术学术交流会论文集
- 【会议名称】北京核学会第十届(2014年)核应用技术学术交流会
- 【会议时间】2014-11-27
- 【会议地点】中国湖北武汉
- 【分类号】TL353.13
- 【主办单位】北京核学会、《原子能科学技术》编辑部