Slip casting of nuclear fuel elements.

"Contract no. AT(30-1)-2258"

Fluidized-Bed Characteristics in the Coating of Nuclear Fuel Particles [electronic resource]

Mode of access: Internet.

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.

Implementation plan for the Department of Energy programmatic spent nuclear fuel management and Idaho National Engineering Laboratory environmental restoration and waste management programs environmental impact statement : October 29, 1993.

Mode of access: Internet.

Amendment to the October 29, 1993 implementation plan for the Department of Energy programmatic spent nuclear fuel management and Idaho National Engineering Laboratory environmental restoration and waste management programs environmental impact statement : May 9, 1994.

Mode of access: Internet.

Department of Energy programmatic spent nuclear fuel management and Idaho National Engineering Laboratory environmental restoration and waste management programs : record of decision /

"May 30, 1995"--Letter of transmittal.

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.

The Illinois Spent Nuclear Fuel and High-Level Waste Inspection and Escort Program /

"5/99"--Colophon.

Illinois spent nuclear fuel transportation.

Mode of access: Internet.

Microstructural evaluation of superheat cladding materials /

"U.S. Atomic Energy Commission Contract AT(04-3)-189, Project agreement 13."

Isostatic pressing of UO₂ in high temperature metals /

The hot isostatic pressing process has been applied at temperatures up to 1500°C for the fabrication of high temperature fuel rods composed of UO₂ clad in columbium and UO₂ in iron-aluminum type alloy. The fused UO₂ powder apparently becomes quite plastic at temperatures above 1200°C and can be isostatically compacted at 1500°C to 98% of its theoretical density. Columbian tubes particularly lend themselves to the fabrication of fuel rods by simultaneously compacting and cladding UO₂ powders in the tubes, but the cast iron-aluminum type alloy that was used was unsatisfactory because of its brittleness.

The effect of nuclear radiation on ceramic reactor-fuel materials /

"June 30, 1963."

The effect of nuclear radiation on metallic fuel materials /

"September 30, 1963."

PWR fuel element specifications.

"Reactors - Power (TID-4500, 13th Edition)."