Target and method for the production of fission product molybdenum-99
Abstract
A target for the reduction of fission product Mo-99 is prepared from uranium of low U-235 enrichment by coating a structural support member with a preparatory coating of a substantially oxide-free substrate metal. Uranium metal is electrodeposited from a molten halide electrolytic bath onto a substrate metal. The electrodeposition is performed at a predetermined direct current rate or by using pulsed plating techniques which permit relaxation of accumulated uranium ion concentrations within the melt. Layers of as much as to 600 mg/cm/sup 2/ of uranium can be prepared to provide a sufficient density to produce acceptable concentrations of fission product Mo-99. 2 figs.
- Inventors:
- Issue Date:
- Research Org.:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- OSTI Identifier:
- 7039974
- Patent Number(s):
- 6112158
- Assignee:
- ANL; EDB-88-179688
- Patent Classifications (CPCs):
-
G - PHYSICS G01 - MEASURING G01R - MEASURING ELECTRIC VARIABLES
G - PHYSICS G06 - COMPUTING G06Q - DATA PROCESSING SYSTEMS OR METHODS, SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL, SUPERVISORY OR FORECASTING PURPOSES
- DOE Contract Number:
- W-31109-ENG-38
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 59 BASIC BIOLOGICAL SCIENCES; 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; MOLYBDENUM 99; PRODUCTION; DESIGN; FISSION PRODUCTS; INVENTIONS; TARGETS; URANIUM 235; ACTINIDE ISOTOPES; ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; DAYS LIVING RADIOISOTOPES; EVEN-ODD NUCLEI; HEAVY NUCLEI; INTERMEDIATE MASS NUCLEI; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; MINUTES LIVING RADIOISOTOPES; MOLYBDENUM ISOTOPES; NUCLEI; RADIOACTIVE MATERIALS; RADIOISOTOPES; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES; 550201* - Biochemistry- Tracer Techniques; 651720 - Nuclear Properties & Reactions, A=90-149, Experimental
Citation Formats
Vandegrift, G F, Vissers, D R, Marshall, S L, and Varma, R. Target and method for the production of fission product molybdenum-99. United States: N. p., 1987.
Web.
Vandegrift, G F, Vissers, D R, Marshall, S L, & Varma, R. Target and method for the production of fission product molybdenum-99. United States.
Vandegrift, G F, Vissers, D R, Marshall, S L, and Varma, R. Mon .
"Target and method for the production of fission product molybdenum-99". United States.
@article{osti_7039974,
title = {Target and method for the production of fission product molybdenum-99},
author = {Vandegrift, G F and Vissers, D R and Marshall, S L and Varma, R},
abstractNote = {A target for the reduction of fission product Mo-99 is prepared from uranium of low U-235 enrichment by coating a structural support member with a preparatory coating of a substantially oxide-free substrate metal. Uranium metal is electrodeposited from a molten halide electrolytic bath onto a substrate metal. The electrodeposition is performed at a predetermined direct current rate or by using pulsed plating techniques which permit relaxation of accumulated uranium ion concentrations within the melt. Layers of as much as to 600 mg/cm/sup 2/ of uranium can be prepared to provide a sufficient density to produce acceptable concentrations of fission product Mo-99. 2 figs.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1987},
month = {10}
}
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