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

Patent · Sun Jan 01 00:00:00 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 (United States)
• 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

Related Subjects

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/