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PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING DECEMBER, 1960
Author(s) -
R.W. Dayton,
C.R. Jr. Tipton
Publication year - 1961
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4054288
Subject(s) - materials science , ceramic , metallurgy , uranium , cermet , enriched uranium , nuclear engineering , engineering
Research areas include: reactor materials and components; alloy fuels; fission-gas release from refractory fuels; fuel-element development; gas-pressure bonding of ceramic, cermet, and dispersion fuel elements; development of uranium carbide; physical research; radioisotope and radiation applications; void- distribution and heattransfer studies; development of uranium mononitride; materials development and evaluation; coated-particle fuel materials; problems associated with recovery of spent fuel elements; pebble-bed reactor materials; development of fabrication processes for cold bonding of Zircaloy-2 to type 410 stninless steel; development and evaluation of fuel elements for MGCR; development studies for SM-2; gas-cooled reactor program; corrosion of thorium and uranium under storage conditions; and gas-pressure bonding of berylliumclad fuel elements. (For preceding period see BMI-1480.) (B.O.G.

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