摘要
针对压水堆堆芯临界热流密度(CHF)预测这一重要科学问题,分析了棒束中存在的格架效应、冷壁效应和非均匀加热效应对CHF的影响,对比了基于不同假设的6类CHF机理模型,给出了棒束CHF关系式的开发途径,并得出了CHF机理模型和经验关系式在棒束CHF预测上的优缺点。建议进一步充实已有的CHF实验数据库,优化CHF关系式的开发方法,并积极开发棒束CHF机理模型。
In order to accurately predict the critical heat flux(CHF)in pressurized water reactor core fuel assembly,the effects of spacer grids,cold walls and non-uniform heat flux in rod bundles on CHF are analyzed.Simultaneously,six CHF mechanism models based on different physical hypothesis are comparatively researched,and the development methods for CHF correlations are put forward.Advantages and disadvantages of CHF mechanism models and empirical correlations in the prediction of bundle CHF are obtained.It is suggested that the expanding of existing CHF experimental database,the optimizing of development methods of CHF correlations,and the developing of rod bundle CHF mechanism models shall be carried out.
作者
刘伟
彭诗念
江光明
刘余
单建强
Liu Wei;Peng Shinian;Jiang Guangming;Liu Yu;Shan Jianqiang(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610041,China;School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an,710049,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2018年第A01期84-87,共4页
Nuclear Power Engineering
基金
基于子通道分析的棒束CHF机理模型研究(6142A0701050217)
关键词
压水堆
临界热流密度(CHF)
机理模型
经验关系式
Pressurized water reactor
Critical heat flux(CHF)
Mechanism model
Empirical correlation