铅基快堆SGTR事故下热工水力模拟及气腔扩散行为研究  

Thermal-hydraulic Simulation and Steam Cavity Diffusion of SGTR Accident in Lead-cooled Fast Reactor

作　　者：于启帆 赵亚峰 王成龙[1] 张大林[1] 田文喜[1] 秋穗正[1] 苏光辉[1] YU Qifan;ZHAO Yafeng;WANG Chenglong;ZHANG Dalin;TIAN Wenxi;QIU Suizheng;SU Guanghui(School of Energy and Power Engineering,Xi’an Jiaotong University,Xi’an 710049,China)

机构地区：[1]西安交通大学能源与动力工程学院,陕西西安710049

出　　处：《原子能科学技术》2022年第10期2015-2023,共9页Atomic Energy Science and Technology

基　　金：国家重点研发计划(2019YFB1901300);国家自然科学基金(11875217);中国核工业集团有限公司领创科研项目。

摘　　要：本文针对铅基快堆蒸汽发生器传热管破裂(SGTR)事故,利用计算流体力学(CFD)程序对LIFUS5/MOD2台架的汽水注射进液态金属铅铋环境进行研究。研究了3种热工水力现象:铅铋环境压力上升与压力波传递,铅池液位波动和气泡夹带与铅池液位上升和蒸汽扩散。研究结果表明:CFD模型在模拟SGTR事故的压力变化和压力波传递方面具有很小的计算误差;压力波峰值会随着水侧背压的升高而增大,且局部的蒸汽腔压力会低于附近的铅池压力,抑制蒸汽爆炸发生;同时事故引起的铅铋液位上升既会引起小尺寸气泡的输运夹带,也会对铅铋环境结构件造成冲击。Lead-cooled fast reactor(LFR)is known as a typical reliable new type reactor by the US Department of Energy(DOE),and the potential accidents of LFR are necessary to assess.Steam generator tube rupture(SGTR)accident can cause high-pressure hyperbaric steam-water jetting into liquid lead bismuth eutectic(LBE)pool,and leads to a rapid pressure rising in the reactor primary system together with a potential pressure wave crashing the structures.This paper focuses on the computational fluid dynamics(CFD)analyses of SGTR experimental research on the LIFUS5/MOD2 experiment facility.A two-dimensional symmetrical slice with 1 million 570 thousand structured mesh was established for the experimental reaction vessel,and each side except the injection nozzle were set as adiabatic no slip boundary in order to achieve the non-decompression process.In the aspect of multiphase model settings,the Eulerian-Eulerian two-phase flow model was adopted to track the steam-LBE interface in the transient simulation,and the CSF surface tension polynomial together with Lee substituted evaporation model were considered.In addition,the injection of high-pressure water in each time step was separated to two parts:latent heat and injected steam,so as to calculate both endothermic and jet of flash evaporation simultaneously.Among them,the latent heat was realized by user-defined functions(UDF),and the injected steam was adopted as compressible real gas with R-K gas state equation.Based on the above settings,three established thermal-hydraulics phenomena including pressure rising of LBE environment together with pressure wave spreading,level fluctuation of liquid environment with argon entrainment and level rising of liquid environment and diffusion of injected steam were analyzed.From the results a conclusion can be reached that CFD numerical simulation has little error on calculating pressure rising with pressure wave spreading.In addition,the peak value of pressure wave rises with back pressure of water increasing,and the pressure of partial st

关 键 词：铅基快堆 蒸汽发生器传热管破裂事故 两相流模型 计算流体力学 

分 类 号：TL425[核科学技术—核技术及应用]