摘要
对反应堆内临界热流密度(CHF)关系式开发中的关键问题(如冷壁效应、非均匀加热因子、数据统计处理等)进行研究,并以公开发表的CHF试验数据为基础,完成自主化CHF关系式初步拟合和关系式限值确定。在对计算结果进行详细统计分析的基础上,建立了一套严密的统计处理方法以确定CHF关系式DNBR限值。
In this paper, the key issues in the development of reactor critical heat flux（CHF） correlation such as cold wall effect, non-uniform heating factor and statistical treatment of data have been studied, and based on the published CHF trial data we completed the localization of CHF correlation fitting and determination of the corresponding limit value. With a detailed statistical analysis of the calculation results, we established a rigorous method to determine the DNBR limits of CHF correlation.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2016年第5期130-134,共5页
Nuclear Power Engineering
