基于THTF稳态传热试验的LOCUST 1.2确认  

Validation of LOCUST 1.2 Against THTF Steady Heat Transfer Experiment

作　　者：袁红胜 徐财红 琚忠云 王婷 曹志伟 YUAN Hongsheng;XU Caihong;JU Zhongyun;WANG Ting;CAO Zhiwei(China Nuclear Power Technology Research Institute Co.,Ltd,No.1001 Shangbu Middle Road,Futian District,Shenzhen of Guangdong Prov.518026,China)

机构地区：[1]中广核研究院有限公司反应堆工程软件研究所,广东深圳518026

出　　处：《核科学与工程》2022年第6期1377-1382,共6页Nuclear Science and Engineering

摘　　要：LOCUST是由中国广核集团有限公司(CGN)开发的热工水力系统分析软件。为支持LOCUST在压水堆LOCA等事故分析中的应用,进行了基于美国橡树岭国家试验室开展的THTF稳态喷放传热试验的确认。模拟和分析的稳态膜沸腾试验工况为3.07.9 B、3.07.9 N、3.07.9 W、3.07.9 H,涵盖了高、低质量流速和高、低压的试验条件。首先给出了试验的简短介绍,然后描述了该试验的LOCUST计算模型,最后通过计算结果与试验数据的比较,得出评估结论。评估结果表明LOCUST预测的CHF位置和棒表面温度总体合理,软件可用于模拟压水堆喷放阶段传热。观察到壁温的差异可能是由高估的夹带或壁传热引起的,进一步确认具体原因需通过测量更多参数(如夹带)的试验进行评估。LOCUST is a thermo-hydraulic system analysis code developed by China General Nuclear Power Corporation(CGN). To support the application of LOCUST in analysis such as PWR LOCA accidents, the validation of LOCUST blowdown heat transfer performance against THTF steady experiments, which was conducted by the Oak Ridge National Laboratory, was carried out. The steady film boiling experiments simulated and reported are tests 3.07.9B,3.07.9N, 3.07.9W, 3.07.9H, which cover the test conditions of high and low mass flux and high and low pressure condition. A short introduction of the experiments is given and then the LOCUST input model of the facility is described. Lastly, the calculation results were compared with data followed by a conclusion of the assessment. The overall reasonable prediction of the CHF position and the rod surface temperature shows that LOCUST can be used to simulate blowdown heat transfer of PWR. Small discrepancy of the wall temperature was observed that can be caused by over predicted entrainment or wall heat transfer, which can only be specified by further assessment with measured parameters such as entrainment.

关 键 词：CHF 膜态沸腾传热 临界后传热 系统程序 

分 类 号：TL33[核科学技术—核技术及应用]