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AQUEOUS PROCESSES FOR DISSOLUTION OF URANIUM-MOLYBDENUM ALLOY REACTOR FUEL ELEMENTS
- L. M. Ferris
- 14 July 1961
Methods for dissolving unirradiated uranium-molybdenum alloy reactcr fuels in nitric acid, nitric acid--ferric nitrate, and nitric acid-- phosphoric acid solutions were studied on a laboratory scale.… Expand
HOT-CELL STUDIES OF AQUEOUS DISSOLUTION PROCESSES FOR IRRADIATED CARBIDE REACTOR FUELS
MOLTEN-SALT BREEDER REACTOR FUEL PROCESSING.
SULFEX-THOREX AND DAREX-THOREX PROCESSES FOR THE DISSOLUTION OF CONSOLIDATED EDISON POWER REACTOR FUEL: LABORATORY DEVELOPMENT
Modified flowsheets, based on laboratory-scale studies, are presented for batch dissolution of Consolidated Edison power reactor fuel. The stainless- steel jacket may be dissolved in either boiling… Expand
Chemical applications of nuclear explosives
Possible tritium behavior during the recovery of oil from shales broken with nuclear explosives was studied by exposing shale samples to tritiated water vapor and recovering oil from the contaminated… Expand
COMBUSTION-DISSOLUTION EXPERIMENTS WITH IRRADIATED GRAPHITE-BASE REACTOR FUEL CONTAINING CARBON-COATED THORIUM-URANIUM DICARBIDE PARTICLES
Four small pieces of simulated HTGR fuel (from the GAIL-IIIA loop experiment) irradiated to approximately 10,000 Mwd/metric ton (U + Th) were burned in oxygen for 5 hr to determine fission product… Expand
Equilibrium distribution of lithium and bismuth between liquid lithium-- bismuth alloys and molten lithium chloride at 650 to 680$sup 0$
DISSOLUTION OF SOL-GEL-DERIVED AND ARC-FUSED ThO$sub 2$-UO$sub 2$ FUEL PARTICLES IN HNO$sub 3$-HF SOLUTIONS: LABORATORY STUDIES
Processing of Graphite Reactor Fuels Containing Coated Particles and Ceramics