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船用反应堆堆芯稳态热工水力分析程序的研制
引用本文:于雷,蔡志明,王少明.船用反应堆堆芯稳态热工水力分析程序的研制[J].海军工程大学学报,2000(5):45-48.
作者姓名:于雷  蔡志明  王少明
作者单位:海军工程大学,动力工程学院,湖北,武汉,430033
摘    要:针对船用反应堆的实际特点,在充分研究欠热沸腾传热的基础上,建立堆芯热工水力模型,研制了船用堆芯稳态热工水力分析程序.程序可用于分析船用反应堆正常工况和某些事故工况下的堆芯热工水力特性.

关 键 词:船用反应堆  堆芯  热工水力
修稿时间:1999-11-12

The development of steady-state analysis code for marine nuclear reactor
YU Lei,CAI Zhi-ming,WANG Shao-ming.The development of steady-state analysis code for marine nuclear reactor[J].Journal of Naval University of Engineering,2000(5):45-48.
Authors:YU Lei  CAI Zhi-ming  WANG Shao-ming
Abstract:According to the characters of marine nuclear power equipment, the steady-state analysis code for marine nuclear reactor is developed. The code, which is based on the advanced mathematical and physical models, particularly the sub-cool boiling heat transfer models can be used to analyze the steady-state thermal-hydraulic behaviors of reactor in normal condition or some accidents.
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