SELECTIVE SEPARATION OF URANIUM FROM FERRITIC STAINLESS STEELS
Abstract
A process is described for separating uranium from a nuclear fuel element comprising a uranium-containing core and a ferritic stainless steel clad by heating said element in a non-carburizing atmosphere at a temperature in the range 850-1050 un. Concent 85% C, rapidly cooling the heated element through the temperature range 815 un. Concent 85% to 650 EC to avoid annealing said steel, and then contacting the cooled element with an aqueous solution of nitric acid to selectively dissolve the uranium. (AEC)
- Inventors:
- Issue Date:
- Research Org.:
- Originating Research Org. not identified
- OSTI Identifier:
- 4727599
- Patent Number(s):
- 3089751
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
- NSA Number:
- NSA-17-021805
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-63
- Country of Publication:
- United States
- Language:
- English
- Subject:
- CHEMISTRY; BURNUP; COOLING; FUEL CANS; FUEL ELEMENTS; HEATING; HIGH TEMPERATURE; NITRIC ACID; REPROCESSING; SEPARATION PROCESSES; SOLUTIONS; STAINLESS STEELS; URANIUM; WATER
Citation Formats
Beaver, R J, and Cherubini, J H. SELECTIVE SEPARATION OF URANIUM FROM FERRITIC STAINLESS STEELS. United States: N. p., 1963.
Web.
Beaver, R J, & Cherubini, J H. SELECTIVE SEPARATION OF URANIUM FROM FERRITIC STAINLESS STEELS. United States.
Beaver, R J, and Cherubini, J H. Tue .
"SELECTIVE SEPARATION OF URANIUM FROM FERRITIC STAINLESS STEELS". United States.
@article{osti_4727599,
title = {SELECTIVE SEPARATION OF URANIUM FROM FERRITIC STAINLESS STEELS},
author = {Beaver, R J and Cherubini, J H},
abstractNote = {A process is described for separating uranium from a nuclear fuel element comprising a uranium-containing core and a ferritic stainless steel clad by heating said element in a non-carburizing atmosphere at a temperature in the range 850-1050 un. Concent 85% C, rapidly cooling the heated element through the temperature range 815 un. Concent 85% to 650 EC to avoid annealing said steel, and then contacting the cooled element with an aqueous solution of nitric acid to selectively dissolve the uranium. (AEC)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1963},
month = {5}
}
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