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

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作者：

State Key Laboratory of Intense Pulsed Radiation Simulation and Effect, Northwest Institute of Nuclear Technology, Xi'an ^{[1
]}

710024, China

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来源：

Hedongli Gongcheng | 1600年 / 5卷 / 34-39期

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摘要：

Code development - Space nuclear reactors - Space reactors - Steady state - Thermal hydraulic parameters - Thermal hydraulics - Thermal-hydraulic analysis - Thermal-hydraulic model

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