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.
- Inventors:
-
- Bolingbrook, IL
- Naperville, IL
- Woodridge, IL
- Hinsdale, IL
- Issue Date:
- Research Org.:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- OSTI Identifier:
- 866998
- Patent Number(s):
- 4839133
- Assignee:
- United States of America as represented by Department of Energy (Washington, DC)
- Patent Classifications (CPCs):
-
G - PHYSICS G21 - NUCLEAR PHYSICS G21G - CONVERSION OF CHEMICAL ELEMENTS
- DOE Contract Number:
- W-31109-ENG-38
- Resource Type:
- Patent
- Country of Publication:
- United States
- Language:
- English
- Subject:
- target; method; production; fission; product; molybdenum-99; reduction; mo-99; prepared; uranium; u-235; enrichment; coating; structural; support; preparatory; substantially; oxide-free; substrate; metal; electrodeposited; molten; halide; electrolytic; bath; electrodeposition; performed; predetermined; direct; current; rate; pulsed; plating; techniques; permit; relaxation; accumulated; concentrations; melt; layers; 600; mg; cm; provide; sufficient; density; produce; acceptable; sufficient density; structural support; fission product; direct current; uranium metal; electrolytic bath; molten halide; /376/205/252/976/
Citation Formats
Vandegrift, George F, Vissers, Donald R, Marshall, Simon L, and Varma, Ravi. Target and method for the production of fission product molybdenum-99. United States: N. p., 1989.
Web.
Vandegrift, George F, Vissers, Donald R, Marshall, Simon L, & Varma, Ravi. Target and method for the production of fission product molybdenum-99. United States.
Vandegrift, George F, Vissers, Donald R, Marshall, Simon L, and Varma, Ravi. Sun .
"Target and method for the production of fission product molybdenum-99". United States. https://www.osti.gov/servlets/purl/866998.
@article{osti_866998,
title = {Target and method for the production of fission product molybdenum-99},
author = {Vandegrift, George F and Vissers, Donald R and Marshall, Simon L and Varma, Ravi},
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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1989},
month = {1}
}
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