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Title: METHOD OF PRODUCING U$sup 23$$sup 3$

Abstract

A method for producing U/sup 233/ is outlined in which a body of thorium carbonate is heated to at least 200 deg C until it attains a constant weight and compressing the body into a pellet having a density of at least 2.6 g/cm/sup 3/. The pellet is enclosed in a sealed container and placed in the blanket of a thermal nuclear reactor having a neutron flux in which the majority of neutrons have an energy of below I Mev. The pellet is removed from the flux before the ratio of U/sup 233/ to Th/sup 232/ is about 1: 100.

Inventors:
;
Issue Date:
OSTI Identifier:
4126322
Patent Number(s):
2951023
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
G - PHYSICS G21 - NUCLEAR PHYSICS G21G - CONVERSION OF CHEMICAL ELEMENTS
NSA Number:
NSA-14-025924
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; BLANKETS; DENSITY; HEATING; NEUTRON FLUX; PATENT; PELLETS; PRESSURE; PRODUCTION; REACTORS; THERMAL NEUTRONS; THORIUM 232; THORIUM CARBONATES; URANIUM 233; VESSELS

Citation Formats

Seaborg, G T, and Stoughton, R W. METHOD OF PRODUCING U$sup 23$$sup 3$. United States: N. p., 1960. Web.
Seaborg, G T, & Stoughton, R W. METHOD OF PRODUCING U$sup 23$$sup 3$. United States.
Seaborg, G T, and Stoughton, R W. Tue . "METHOD OF PRODUCING U$sup 23$$sup 3$". United States.
@article{osti_4126322,
title = {METHOD OF PRODUCING U$sup 23$$sup 3$},
author = {Seaborg, G T and Stoughton, R W},
abstractNote = {A method for producing U/sup 233/ is outlined in which a body of thorium carbonate is heated to at least 200 deg C until it attains a constant weight and compressing the body into a pellet having a density of at least 2.6 g/cm/sup 3/. The pellet is enclosed in a sealed container and placed in the blanket of a thermal nuclear reactor having a neutron flux in which the majority of neutrons have an energy of below I Mev. The pellet is removed from the flux before the ratio of U/sup 233/ to Th/sup 232/ is about 1: 100.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1960},
month = {8}
}