摘要
核一级设备的瞬态热分析结果对结构的疲劳、断裂分析评价具有重要影响,而热分析的关键环节是精确确定冷却剂与容器表面之间界面处的热交换系数。本文采用ANSYS用户子程序USERCV实现有限元分析中底层数据的交换,最终实现换热系数的准确施加。本文介绍了USERCV子程序的编写、编译与连接,并结合具体算例给出了应用过程。从结果对比可以看出,USERCV子程序能在一定程度上减少断裂力学评定和疲劳分析的保守性。
The thermal transient analysis result of the nuclear components contributes significant effect to the fatigue and fracture mechanics evaluation, and the key step of thermal analysis procedure is to apply the precise film coefficient. In this paper, the implement of applying the precise film coefficient is realized by using ANSYS user subroutine USERCV. The coding of USERCV subroutine, compiling and linking, application with example are also given in detail in this paper. Based on the comparison of the calculation, it is obvious that USERCV can reduce the conservative of fracture mechanic evaluation and fatigue analysis in a certain extent. © 2015, Editorial Office of Nuclear Power Engineering. All right reserved.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2015年第S2期127-130,共4页
Nuclear Power Engineering