摘要
针对快堆结构,自主开发了适用于CFR600快堆热工水力设计及优化的程序,并进行了相关测试验证。结果表明,该程序具备快堆全堆图形建模、精细化子通道自动划分、考虑组件间换热的热工水力分析以及流量自动分区优化等功能,可为后续自主知识产权的商业快堆技术研发提供支持。
A code was developed for CFR600 fast reactor core thermal-hydraulics design and optimization,and was tested and validated.It supplies the abilities such as quick modelling of full core by GUI(graphical user interface),automatic fine sub-channel meshing,thermal-hydraulic analysis considering heat transfer among neighbor assemblies,and automatically optimizing flow zoning.Furthermore,it will be used to support the independent intellectual technology innovation of commercial fast reactor power plant.
作者
周志伟
杨红义
李淞
林超
ZHOU Zhiwei;YANG Hongyi;LI Song;LIN Chao(China Institute of Atomic Energy,P.O.Box 275-95,Beijing 102413,China)
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2018年第1期56-63,共8页
Atomic Energy Science and Technology
作者简介
周志伟（1986—），男，湖南隆回人，硕士研究生，核能科学与工程专业
