Tritium Transient and Sensitivity Analysis of Tritium Extraction Experiment (TEX) PbLi Loop Using MELCOR-TMAP
IEEE TRANSACTIONS ON PLASMA SCIENCE（2024）
Key words
Deuterium,Solid modeling,Mathematical models,Safety,Codes,Computational modeling,Boundary conditions,Computational modeling,fusion reactors,MELCOR,MELCOR-TMAP,modeling,nuclear and plasma,nuclear power generation,safety,system analysis and design,Tritium Extraction eXperiment (TEX),tritium transport
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