非能动IVR-ERVC试验装置的流动特性初步研究  

Preliminary analysis of channel flow characteristics in the passive IVR-ERVC experimental facility

作　　者：唐超力 匡波[1] 刘鹏飞[1] 朱晨[1] 王凡[1] 

机构地区：[1]上海交通大学核科学与工程学院,上海200240

出　　处：《核技术》2014年第12期59-66,共8页Nuclear Techniques

基　　金：国家自然科学基金(No.51076091);重大专项ERVC全尺寸下封头外壁临界热通量和流道流动试验(No.2010ZX06002-004)资助

摘　　要：本文采用RELAP5/MOD3对全高度非能动的压力容器外部冷却(External Reactor Vessel Cooling,ERVC)一维传热与流动特性试验装置REPEC-II,进行了装置流道流动特性的预测计算,并结合REPEC-II的部分工况的试验结果,初步分析了ERVC流道的自然循环能力与循环流动特性。计算结果与实测数据之间一致性较好;可视化观测与计算、实测结果之间互相印证,揭示了部分流道流动及不稳定性机理特征;运用模拟与预测计算还可进一步研究装置的流道流动特性,并用于后续试验与应用的规划与优化。Background： Through External Reactor Vessel Cooling （ERVC） to achieve the aim of In-Vessel Retention （IVR） is an important severe accident mitigation measure. After the Fukushima nuclear power plant severe accident, IVR-ERVC gains more and more attention. A full-scale IVR-ERVC engineering verification facility REPEC-II was constructed by Shanghai Jiao Tong University. Purpose： To study in-vessel retention by external reactor vessel cooling in large-scale advanced pressurized water reactor under severe accident conditions and meet the demand of verifying the validity of severe accident mitigation. Methods： The flow characteristics of the passages in some parts of the experiment conditions were calculated by RELAP5/MOD3. The natural circulation flow capabilities and features and the typical flashing eruption phenomenon in the experiment on the REPEC-II were preliminarily analyzed. Results and Conclusion： Comparative analysis showed that the calculated results were consistent well with the measured data and visual observation, and basically reflected the reliability of the calculations. Preliminary indication of the flow characteristics of the facility can be further analyzed in-depth, and applied to plan of follow-up experiments.

关 键 词：IVR-ERVC 流道流动特性 工程验证试验 RELAP5 

分 类 号：TL364[核科学技术—核技术及应用]