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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Hedongli Gongcheng | 1600年 / 5卷 / 34-39期
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Compilation and indexing terms; Copyright 2024 Elsevier Inc;
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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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