Feasibility study to increase the reactor power at natural convection mode in Tehran Research Reactor (TRR) through a hybrid thermal-hydraulic simulation and analysis using the RELAP5 code and Computational Fluid Dynamic (CFD) modeling by ANSYS-FLUENT

Progress in Nuclear Energy - Tập 150 - Trang 104285 - 2022
Afshin Hedayat1, Amin Davari1
1Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute (NSTRI), End of North Karegar Street, P.O. Box 14395-836, Tehran, Iran

Tài liệu tham khảo

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