DECONTAMINATION OF URANIUM
Abstract
This patent deals with the separation of rare earth and other fission products from neutron bombarded uranium. This is accomplished by melting the uranium in contact with either thorium oxide, maguesium oxide, alumnum oxide, beryllium oxide, or uranium dioxide. The melting is preferably carried out at from 1150 deg to 1400 deg C in an inert atmosphere, such as argon or helium. During this treatment a scale of uranium dioxide forms on the uranium whtch contains most of the fission products.
- Inventors:
- Issue Date:
- OSTI Identifier:
- 4343445
- Patent Number(s):
- 2822260
- 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 G21C - NUCLEAR REACTORS
- NSA Number:
- NSA-12-010241
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-58
- Country of Publication:
- United States
- Language:
- English
- Subject:
- PATENTS; ALUMINUM OXIDES; ARGON; BERYLLIUM OXIDES; DECONTAMINATION; FISSION PRODUCTS; HIGH TEMPERATURE; INERT GASES; MAGNESIUM OXIDES; MELTING; NEUTRON BEAMS; PATENT; RARE EARTHS; THORIUM OXIDES; URANIUM; URANIUM DIOXIDE
Citation Formats
Feder, H M, and Chellew, N R. DECONTAMINATION OF URANIUM. United States: N. p., 1958.
Web.
Feder, H M, & Chellew, N R. DECONTAMINATION OF URANIUM. United States.
Feder, H M, and Chellew, N R. Sat .
"DECONTAMINATION OF URANIUM". United States.
@article{osti_4343445,
title = {DECONTAMINATION OF URANIUM},
author = {Feder, H M and Chellew, N R},
abstractNote = {This patent deals with the separation of rare earth and other fission products from neutron bombarded uranium. This is accomplished by melting the uranium in contact with either thorium oxide, maguesium oxide, alumnum oxide, beryllium oxide, or uranium dioxide. The melting is preferably carried out at from 1150 deg to 1400 deg C in an inert atmosphere, such as argon or helium. During this treatment a scale of uranium dioxide forms on the uranium whtch contains most of the fission products.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1958},
month = {2}
}
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.