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Title: PROCESS OF MAKING SHAPED FUEL FOR NUCLEAR REACTORS

Abstract

A process for making uranium dioxide fuel of great strength, density, and thermal conductivity by mixing it with 0.1 to 1% of a densifier oxide (tin, aluminum, zirconium, ferric, zinc, chromium, molybdenum, titanium, or niobium oxide) and with a plasticizer (0.5 to 3% of bentonite and 0.05 to 2% of methylcellulose, propylene glycol alginate, or ammonium alginate), compacting the mixture obtained, and sintering the bodies in an atmosphere of carbon monoxide or carbon dioxide, with or without hydrogen, or of a nitrogen-hydrogen mixture is described. (AEC)

Inventors:
;
Issue Date:
OSTI Identifier:
4103237
Patent Number(s):
3121128
Assignee:
U.S. Atomic Energy Commission
Patent Classifications (CPCs):
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y10 - TECHNICAL SUBJECTS COVERED BY FORMER USPC Y10S - TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
NSA Number:
NSA-18-010516
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-64
Country of Publication:
United States
Language:
English
Subject:
METALS, CERAMICS, AND OTHER MATERIALS; CARBON DIOXIDE; CARBON MONOXIDE; COMPACTING; DENSITY; DUCTILITY; HYDROGEN; MIXING; NITROGEN; OXIDES; SINTERING; THERMAL CONDUCTIVITY; URANIUM DIOXIDE

Citation Formats

O'Leary, W J, and Fisher, E A. PROCESS OF MAKING SHAPED FUEL FOR NUCLEAR REACTORS. United States: N. p., 1964. Web.
O'Leary, W J, & Fisher, E A. PROCESS OF MAKING SHAPED FUEL FOR NUCLEAR REACTORS. United States.
O'Leary, W J, and Fisher, E A. Tue . "PROCESS OF MAKING SHAPED FUEL FOR NUCLEAR REACTORS". United States.
@article{osti_4103237,
title = {PROCESS OF MAKING SHAPED FUEL FOR NUCLEAR REACTORS},
author = {O'Leary, W J and Fisher, E A},
abstractNote = {A process for making uranium dioxide fuel of great strength, density, and thermal conductivity by mixing it with 0.1 to 1% of a densifier oxide (tin, aluminum, zirconium, ferric, zinc, chromium, molybdenum, titanium, or niobium oxide) and with a plasticizer (0.5 to 3% of bentonite and 0.05 to 2% of methylcellulose, propylene glycol alginate, or ammonium alginate), compacting the mixture obtained, and sintering the bodies in an atmosphere of carbon monoxide or carbon dioxide, with or without hydrogen, or of a nitrogen-hydrogen mixture is described. (AEC)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1964},
month = {2}
}