Open AccessDESIGN OF NAA-62-2
Author(s) -
H. B. Brooks
Publication year - 1963
Language(s) - English
Resource type - Reports
DOI - 10.2172/4003217
Subject(s) - nuclear engineering , neutron flux , flux (metallurgy) , series (stratigraphy) , presentation (obstetrics) , neutron , computer science , engineering , materials science , nuclear physics , physics , geology , paleontology , metallurgy , medicine , radiology
A series of in-pile experiments was designed for evaluation of a prototype fuel element to operate under approximate ASCR conditions. The fuel surface temperature will be automatically controlled by means of a BF/sub 3/ thermal neutron flux control system. Complete design calculations and results are presented, which should be adequate for presentation of the experiment to the ETR safety committee. (auth
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