Neutronics and thermal-hydraulics coupling analysis using...

Nuclear Engineering and Design 2020 / 11 Vol. 368

Neutronics and thermal-hydraulics coupling analysis using the FLUENT code and the RELAP5-3D code for a molten salt fast reactor

Mochizuki, Hiroyasu
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Volume:
368
Journal:
Nuclear Engineering and Design
DOI:
10.1016/j.nucengdes.2020.110793
Date:
November, 2020
File:
PDF, 4.21 MB
2020
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