Open AccessTHE FABRICATION OF THE FUEL ELEMENTS FOR THE TRANSIENT REACTOR TEST. Program 7.6.9
Author(s) -
C.H. Bean,
F.D. McCuaig,
J.H. Handwerk
Publication year - 1959
Language(s) - English
Resource type - Reports
DOI - 10.2172/4227065
Subject(s) - fluence , extrapolation , nuclear engineering , neutron flux , irradiation , neutron , materials science , fabrication , transient (computer programming) , nuclear physics , radiochemistry , chemistry , physics , engineering , computer science , mathematics , medicine , mathematical analysis , alternative medicine , pathology , operating system