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
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State Key Laboratory of Intense Pulsed Radiation Simulation and Effect, Northwest Institute of Nuclear Technology, Xi'an
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710024, China
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710024, China
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来源:
Hedongli Gongcheng
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1600年
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5卷
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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