Development of Code for Steady-State Thermal-Hydraulic Analysis in Bimodal Space Nuclear Reactor with Heat Pipe

被引:0
|
作者
State Key Laboratory of Intense Pulsed Radiation Simulation and Effect, Northwest Institute of Nuclear Technology, Xi'an [1 ]
710024, China
机构
来源
Hedongli Gongcheng | 1600年 / 5卷 / 34-39期
关键词
Compilation and indexing terms; Copyright 2024 Elsevier Inc;
D O I
暂无
中图分类号
学科分类号
摘要
Code development - Space nuclear reactors - Space reactors - Steady state - Thermal hydraulic parameters - Thermal hydraulics - Thermal-hydraulic analysis - Thermal-hydraulic model
引用
收藏
相关论文
empty
未找到相关数据