
QUARTERLY PROGRESS REPORT JANUARY, FEBRUARY, MARCH, 1967 REACTOR FUELS AND MATERIALS DEVELOPMENT PROGRAMS FOR FUELS AND MATERIALS BRANCH OF USAEC DEVISION OF REACTOR DEVELOPMENT AND TECHNOLOGY
Author(s) -
F. W. Albaugh,
S. H. Bush,
J. J. Cadwell,
D.R. de Halas,
D. C. Worlton
Publication year - 1967
Language(s) - English
Resource type - Reports
DOI - 10.2172/1088230
Subject(s) - nuclear engineering , materials science , ceramic , nuclear reactor , nitride , graphite , environmental science , waste management , engineering , metallurgy , nanotechnology , layer (electronics)
Work is reported in the areas of: fast fuels oxides and nitrides; nuclear ceramics; nuclear graphite; basic swelling studies; irradiation damage to reactor metals; ATR gas loop operation and maintenance; metallic fuels; nondestructive testing research; and fast reactor dosimetry and damage analysis