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.

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.

International nuclear spent fuel storage programs : hearing before the Subcommittees on International Security and Scientific Affairs and on International Economic Policy and Trade of the Committee on Foreign Affairs, House of Representatives, Ninety-sixth Congress, first session, May 3, 1979.

Mode of access: Internet.

Nuclear energy and world fuel prices.

Bibliographical footnotes.

Reprocessing of irradiated fission reactor fuel and breeding material : a literature search /

May 1, 1959.

Reprocessing of irradiated fission reactor fuel and breeding material : a literature search /

"January 1960."

Reprocessing of irradiated fission reactor fuel and breeding material : a literature search /

"October 1961."

Fuel breeding : a literature search /

"August 1959."

Scoping assessment of the environmental health risk associated with accidents in the LWR supporting fuel cycle /

Issued Feb. 1977.

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."

In-pile loop test for the pebble bed reactor fuel development program : final report /

"Final report to Sanderson and Porter for subcontract no. S-3 under USAEC Prime Contract no. AT(30-1)-2378."

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.

The coal future : economic and technological analysis of initiatives and innovations to secure fuel supply independence /

Includes bibliographies.