Open AccessTHR-TH: a high-temperature gas-cooled nuclear reactor core thermal hydraulics code
Author(s) -
D.R. Vondy
Publication year - 1984
Language(s) - Uncategorized
Resource type - Reports
DOI - 10.2172/6626209
Subject(s) - neutron transport , thermal hydraulics , nuclear engineering , hydraulics , coolant , nuclear reactor core , core (optical fiber) , heat transfer , mechanics , environmental science , nuclear physics , engineering , physics , neutron , thermodynamics , telecommunications