DOE Patents title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: 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:
 [1];  [2];  [3];  [4]
  1. Bolingbrook, IL
  2. Naperville, IL
  3. Woodridge, IL
  4. Hinsdale, IL
Issue Date:
Research Org.:
Argonne National Lab. (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}
}