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Title: METHOD OF FABRICATING A URANIUM-ZIRCONIUM HYDRIDE REACTOR CORE

Abstract

A method is described of evenly dispersing uranlum metal in a zirconium hydride moderator to produce a fuel element for nuclear reactors. According to the invention enriched uranium hydride and zirconium hydride powders of 200 mesh particle size are thoroughly admixed to form a mixture containing 0.1 to 3% by weight of U/sup 235/ hydride. The mixed powders are placed in a die and pressed at 100 tons per square inch at room temperature. The resultant compacts are heated in a vacuum to 300 deg C, whereby the uranium hydride deoomposes into uranium metal and hydrogen gas. The escaping hydrogen gas forms a porous matrix of zirconium hydride, with uramum metal evenly dispersed therethrough. The advantage of the invention is that the porosity and uranium distribution of the final fuel element can be more closely determined and controlled than was possible using prior methods of producing such fuel ele- ments.

Inventors:
;
Issue Date:
OSTI Identifier:
4183947
Patent Number(s):
2929707
Assignee:
U.S. Atomic Energy Commission
Patent Classifications (CPCs):
C - CHEMISTRY C22 - METALLURGY C22C - ALLOYS
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
NSA Number:
NSA-14-015973
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English
Subject:
METALS, CERAMICS, AND OTHER MATERIALS; BEARINGS; CARBON 14; CARBON DIOXIDE; COMBUSTION; COMPACTING; CONTROL; COUNTERS; DECOMPOSITION; DIES; DISPERSIONS; DISTRIBUTION; EFFICIENCY; FABRICATION; FUEL ELEMENTS; GASES; HEATING; HYDROGEN; MIXING; MODERATORS; POROSITY; POWDERS; PRESSURE; QUANTITATIVE ANALYSIS; REACTOR CORE; REACTORS; TEMPERATURE; TRITIUM; URANIUM; URANIUM 235; URANIUM HYDRIDES; VACUUM; WATER; ZIRCONIUM HYDRIDES

Citation Formats

Weeks, I F, and Goeddel, W V. METHOD OF FABRICATING A URANIUM-ZIRCONIUM HYDRIDE REACTOR CORE. United States: N. p., 1960. Web.
Weeks, I F, & Goeddel, W V. METHOD OF FABRICATING A URANIUM-ZIRCONIUM HYDRIDE REACTOR CORE. United States.
Weeks, I F, and Goeddel, W V. Tue . "METHOD OF FABRICATING A URANIUM-ZIRCONIUM HYDRIDE REACTOR CORE". United States.
@article{osti_4183947,
title = {METHOD OF FABRICATING A URANIUM-ZIRCONIUM HYDRIDE REACTOR CORE},
author = {Weeks, I F and Goeddel, W V},
abstractNote = {A method is described of evenly dispersing uranlum metal in a zirconium hydride moderator to produce a fuel element for nuclear reactors. According to the invention enriched uranium hydride and zirconium hydride powders of 200 mesh particle size are thoroughly admixed to form a mixture containing 0.1 to 3% by weight of U/sup 235/ hydride. The mixed powders are placed in a die and pressed at 100 tons per square inch at room temperature. The resultant compacts are heated in a vacuum to 300 deg C, whereby the uranium hydride deoomposes into uranium metal and hydrogen gas. The escaping hydrogen gas forms a porous matrix of zirconium hydride, with uramum metal evenly dispersed therethrough. The advantage of the invention is that the porosity and uranium distribution of the final fuel element can be more closely determined and controlled than was possible using prior methods of producing such fuel ele- ments.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1960},
month = {3}
}