Columbium alloy clad uranium carbide fuel element : final report [covering the period] May 1, 1959-April 30, 1960 /

"Contract no. AT-(40-1)-2559."

Columbium alloy clad uranium carbide fuel element : technical report no. 61-33 /

Work conducted at the Metals Research Laboratories, Union Carbide Metals Company, a Division of Union Carbide Corporation, under the United States Atomic Energy Commission contract no. AT-(40-1)-2559.

Uranium dioxide fuel materials with improved thermal conductivity /

Work performed at the Sylvania-Corning Nuclear Corporation under contract AT (30-1) GEN-366 with the Division of Reactor Development.

Enriched uranium fuel materials : a bibliography of unclassified literature /

Unclassified reports on processing of enriched UF₆ into U metal, U-base alloys, UO₂, and UO₂SO₄ for use a reactor fuels are annotated. Recovery of enriched U scrap, methods of isotopic analysis, health physics, criticality problems, and materials management are emphasized. A few references to papers presented at the Geneva Conference, 1955, and other recent nonreport literature are included. 254 references.

Quantitative determination of uranium loading of aluminum-clad fuel plates by x-ray densitometry /

Work performed at the Sylvania-Corning Nuclear Corporation under Contract AT(30-1) GEN-366.

Uranium fuel cycle radiation protection requirements : environmental impact statement.

F available only in microfiche.

Allocation of uranium enrichment services to fuel foreign and domestic nuclear reactors, Energy Research and Development Administration, Department of State : report to the Committee on Foreign Affairs, House of Representatives /

Publication date stamped on cover.

The determination of uranium isotope abundances and reactor fuel burnup by mass spectrometry /

April 17, 1963--page 11.

Reprocessing of irradiated fission reactor fuel and breeding materials : an annotated bibliography of selected report literature /

"Chemistry--Separation process for plutonium and uranium."

Reprocessing of irradiated fission reactor fuel and breeding materials : an annotated bibliography of selected report literature /

"Chemistry--Separation process for plutonium and uranium."

An evaluation of Dynapak (HERF) extruded uranium tubes /

"AEC Contract No. AT-(30-1)-1405."

Major factors affecting burn-up of nuclear fuel elements /

Uranium oxide has been reduced by carbon under vacuum at 2250°C, to yield a product consisting of dendritic uranium carbide in a matrix of uranium.