Open AccessAdvanced neutron source reactor thermal-hydraulic test loop facility description
Author(s) -
D.K. Felde,
G. Farquharson,
J.H. Hardy,
James King,
M.T. McFee,
B.H. Montgomery,
R.E. Pawel,
Bright Power,
A.A. Shourbaji,
M. Siman-Tov,
R. J. Wood,
G.L. Yoder
Publication year - 1994
Language(s) - Uncategorized
Resource type - Reports
DOI - 10.2172/10140260
Subject(s) - coolant , thermal hydraulics , materials science , nuclear reactor core , oak ridge national laboratory , heat flux , nuclear engineering , core (optical fiber) , mechanics , heat transfer , composite material , nuclear physics , physics , engineering
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