Open AccessHeat transfer analysis of plate type fuel element of reactor core
Author(s) -
Reinaldy Nazar,
Jupiter Sitorus Pane,
Ketut Kamajaya
Publication year - 2018
Publication title -
aip conference proceedings
Language(s) - English
Resource type - Conference proceedings
eISSN - 1551-7616
pISSN - 0094-243X
DOI - 10.1063/1.5046615
Subject(s) - triga , nuclear engineering , coolant , materials science , control rod , neutron flux , nuclear reactor core , research reactor , irradiation , void (composites) , core (optical fiber) , heat transfer , nuclear physics , composite material , mechanics , neutron , engineering , physics
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