Авторы, Редакторы, Рецензенты

Ae-Ju Cheong

Korea Institute of Nuclear Safety 62 Gwahak-ro, Yuseong-gu, Daejeon, 34142, Republic of Korea
Больше информации об авторе - в Directory of Specialists

Articles

CFD analysis of thermal hydraulic behavior in moderator of PHWR Vol. 6 '2018 - 3rd Thermal and Fluids Engineering Conference (TFEC)
EVALUATION OF TURBULENCE AND MASS TRANSFER MODELS ON SCALAR DISPERSION IN TURBULENT ANNULAR FLOW Vol. 0 '2014 - ICHMT DIGITAL LIBRARY ONLINE
A Numerical Study on the Effect of the Mixing Vane Arrangement Patterns on the Heat Removal Capability inside the Fuel Assembly Vol. 19 '2017 - Second Thermal and Fluids Engineering Conference