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

Patent · Tue Jun 13 04:00:00 EDT 1989

OSTI ID:5417336

Vandergrift, G F; Vissers, D R; Marshall, S L; Varma, R

This patent describes a target for the reduction of fission product Mo-99. It 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 electrode-position 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.

• Assignee: Dept. of Energy, Washington, DC
• Patent Number(s): US 4839133
• Application Number: PPN: US 7112158A
• OSTI ID: 5417336
• Country of Publication: United States
• Language: English

Related Subjects

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY
400400 -- Electrochemistry
400703* -- Radiochemistry & Nuclear Chemistry-- Radioisotope Production
652020 -- Nuclear Properties & Reactions
A=220 & above
Experimental
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
DAYS LIVING RADIOISOTOPES
DEPOSITION
ELECTRODEPOSITION
ELECTROLYSIS
ENRICHMENT
EVEN-ODD NUCLEI
FISSION PRODUCTS
INTERMEDIATE MASS NUCLEI
ISOTOPES
LYSIS
MATERIALS
MOLYBDENUM 99
MOLYBDENUM ISOTOPES
NUCLEI
PRODUCTION
PULSE TECHNIQUES
RADIOACTIVE MATERIALS
RADIOISOTOPES
SURFACE COATING
TARGETS
TECHNOLOGY ASSESSMENT
URANIUM 235 TARGET