Target and method for the production of fission product molybdenum-99

Patent · Sun Jan 01 04:00:00 EST 1989

OSTI ID:866998

Vandegrift, George F ^[1]; Vissers, Donald R ^[2]; Marshall, Simon L ^[3]; Varma, Ravi ^[4]

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1. Bolingbrook, IL
2. Naperville, IL
3. Woodridge, IL
4. Hinsdale, IL

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.

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL
• DOE Contract Number: W-31109-ENG-38
• Assignee: United States of America as represented by Department of Energy (Washington, DC)
• Patent Number(s): US 4839133
• OSTI ID: 866998
• Country of Publication: United States
• Language: English

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/376/205/252/976/
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enrichment
fission
fission product
halide
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performed
permit
plating
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preparatory
prepared
produce
product
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provide
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structural
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substantially
substrate
sufficient
sufficient density
support
target
techniques
u-235
uranium
uranium metal