第36卷第4期 2016年8月
核科学与工程
Nuclear Science and Engineering
Vol.36No.4
Aug.2016
燃料棒束换热（RBHT)试验对低压下
堆芯漂移流模型的评价
樊普，曹克美，徐财红（上海核工程研究设计院，上海200233）
摘要：我国目前正在发展基于非能动技术的三代核电，为评价和改进非能动核电厂小破口失水事故在低压下棒束区的漂移流模型，采用燃料棒束换热（RBHT）试验对EPRT()、Cunningham-Yeh4)模型 Bestion刀漂移流模型进行了计算分析，结果表明燃料棒束换热试验RBHT试验数据工况能涵盖非能动
模型基本适用，而EPRI)在低压区过高预测了空泡份额，不适用非能动核电厂。关键调：漂移流模型；失水事故；非能动核电厂
中图分类号：TL364
文章标志码：A
文章编号：0258-0918(2016)04-0548-07
Theevaluationofrodbundledriftfluxmodel usingtheRodBundleHeatTransfer(RBHT)test
FANPu,CAOKe-mei,XU Cai-hong
(Shanghai Nuclear Engineering Research &. Design Institute,Shanghai 200233,China)
Abstract:Passive Nuclear Power Plant is developed in China now.To evaluate and improve the drift flux model in the rod bundle region under low pressure condition, EPRI[),Cunningham-Yeh+,Bestion) model is evaluated using the RBHT(Rod Bundle Heat Transfer)test data.And the RBHT(Rod Bundle Heat Transfer)test data ranges can include the passive nuclear power plant conditions under the low pressure phase of Small Break Loss of Coolant Accident(SBLOCA)scenario. The results indicate that the model of Cunningham-Yeh* and Bestiont* which are used in SBLOCA code for passive nuclear power plant is applicable,and EPRItis not applicable for SBLOCA code of passivenuclear power plantunderlow pressure condition.
Key words: Drift Flux Model;Loss of Coolant Accident;Passive Nuclear Power Plant
为确保核电厂安全运行，正确理解电厂的修回日期：2015-11-30
热工水力行为是非常重要的。系统热工水力程
作者简介：契普（1978一），女，河南南阳人，高级工程师，博士学位，现主要从事非能动核电厂小破口事故分析 548