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Approximate simulation technique for thermal and hydraulic parameters of a reactor core
Approximate simulation technique for thermal and hydraulic parameters of a reactor core
1975
M. K. Gorchakov
A.P. Kolmakov
Yu.S. Yurev
Keywords:
Mechanics
Nuclear reactor core
Thermal
Materials science
Forced convection
Convection
Heat transfer
Differential equation
Natural convection
Equations of motion
Correction
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