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Publications by W. H. McCarthy
Performance of Unencapsulated (U,Pu)O$sub 2$ Fuel Pins (Series F3A) Irradiated in EBR-II to 50,000 MWd/Te.
Related publications
(Pu,U)O$sub 2$--Sodium REACTIONS: EFFECT OF FUEL PARAMETERS.
Exposed-Fuel Calibration Study in Ebr-Ii, Second Series.
POST-IRRADIATION EXAMINATION OF HIGH-DENSITY (UPu)C PELLET-FUELED EBR-II RODS IRRADIATED TO 30,000 MWD/T.
Characterization of Irradiated Metal Waste From the Pyrometallurgical Treatment of Used EBR-II Fuel
Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science
Mechanics of Materials
Alloys
Condensed Matter Physics
Metals
Tritium Retention in EBR-II-irradiated Boron Carbide
METALLOGRAPHY OF IRRADIATED UO$sub 2$-Containing FUEL ELEMENTS
Properties of U Sub 3 O Sub 8 -Aluminum Cermet Fuel
Cs--U--O Phase Diagram and Its Application to Uranium--Plutonium Oxide Fast Reactor Fuel Pins
Loading Diagrams of Experimental Subassemblies Irradiated in Ebr-Ii Runs 5 Through 42.
