摘要
基于日本氚安全研究沉箱(CATS)的氚泄漏实验进行氚系统操作室的氚气泄漏扩散及应急通风计算流体动力学仿真分析,研究中建立了基于释放特征函数的泄漏模型、基于组分的输运模型,通过求解Navier-Stokes方程和采用Realizable的k-ε模型,模拟了氚释放到密闭沉箱后的初始输运过程及其通风去除的输运过程。数值结果与CATS收集的实验数据进行了对比验证,结果表明,沉箱中的局部速度能够较好地表征实验中相关位置的流场速度;对于氚在沉箱中的初始输运过程预测误差最大约为20%,最小仅为1.47%;对于氚的通风去除过程也能够进行较好的预测,此外通过与均匀假设的集总法结果对比,发现集总法预测仅在沉箱为完美混合流时精度较高,但到了排风后期氚很难在沉箱中满足均匀假设,此时应该用计算流体动力学(CFD)模型进行沉箱中的浓度预测。
Based on the tritium leakage behavior experiment of caisson assembly for tritium safety study(CATS)in Japan,computational fluid dynamics simulation analysis of tritium gas leakage,diffusion and emergency ventilation in the tritium system operation room was carried out.A leakage model based on the release characteristic function and a component-based transport model were established in the study.By solving the Navier-Stokes equations and using the realizable k-εmodel,the initial behavior of tritium after being released into the closed caisson and its removal behavior under ventilation conditions were simulated.The numerical results were compared and verified with the experimental data collected by CATS.The results show that the local velocity in the caisson can better characterize the flow field velocity at the relevant position in the experiment;the maximum prediction error of the initial behavior of tritium in the caisson is about 20%,and the minimum is only 1.47%;the ventilation removal behavior of tritium can also be well predicted.In addition,by comparing with the results of the lumped method with the uniform assumption,it is found that the lumped method prediction is only accurate when the caisson is a perfect mixed flow,but in the later stage of exhaust,it is difficult for tritium to meet the uniform assumption in the caisson.At this time,the CFD model should be used to predict the concentration in the caisson.
作者
王宁
刘哲
杨亚鹏
喻豪
WANG Ning;LIU Zhe;YANG Yapeng;YU Hao(Institute of Nuclear Emergency and Nuclear Safety,China Institute for Radiation Protection,Taiyuan of Shanxi Prov.030000,China;CNNC Key Laboratory for Radiation Protection Technology,China Institute for Radiation Protection,Taiyuan of Shanxi Prov.030000,China)
出处
《核科学与工程》
北大核心
2025年第3期519-526,共8页
Nuclear Science and Engineering
关键词
氚系统操作室
氚泄漏
应急通风
泄漏模型
输运模型
初始
去除
Tritium system handling room
Tritium leakage
Emergency ventilation
Leakage model
transport model
Initial behavior
Removal behavior
