Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Controlling Pu behavior on Titania: Implications for LEU Fission-Based Mo-99 Production

Journal Article · · Industrial and Engineering Chemistry Research
 [1];  [1];  [1];  [1]
  1. Nuclear Engineering Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439, United States
Molybdenum-99 is the parent isotope of the most widely used isotope, technetium-99m, in all diagnostic nuclear medicine procedures. Due to proliferation concerns associated with the use of highly enriched uranium (HEU), the preferred method of fission-based Mo-99 production uses low enriched uranium (LEU) targets. Using LEU versus HEU for Mo-99 production produces similar to 30 times more Pu-239, due to neutron capture on U-238 to produce Np-239, which ultimately decays to Pu-239 (t(1/2) = 24,110 yr). Argonne National Laboratory is supporting a potential US Mo-99 producer in their efforts to produce Mo-99 from an LEU solution. In order to mitigate the generation of large volumes of greater-than-class-C (GTCC) low level waste (Pu-239 concentrations greater than 1 nCi/g), we have focused our efforts on the separation chemistry of Pu and Mo with a titania sorbent in sulfate media. Results from batch and column experiments show that temperature and acid wash concentration can be used to control Pu behavior on titania.
Research Organization:
Argonne National Laboratory (ANL)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation (NA-20)
DOE Contract Number:
AC02-06CH11357
OSTI ID:
1417840
Journal Information:
Industrial and Engineering Chemistry Research, Journal Name: Industrial and Engineering Chemistry Research Journal Issue: 40 Vol. 56; ISSN 0888-5885
Publisher:
American Chemical Society (ACS)
Country of Publication:
United States
Language:
English

Similar Records

Development of LEU targets for {sup 99}Mo production and their chemical processing status 1993
Conference · Fri Oct 01 00:00:00 EDT 1993 · OSTI ID:10189026

Irradiation of 20L LEU Uranyl Sulfate Solution for Production of Mo-99
Technical Report · Thu Apr 01 00:00:00 EDT 2021 · OSTI ID:1781392

Continuing investigations for technology assessment of /sup 99/Mo production from LEU (low enriched Uranium) targets
Conference · Wed Dec 31 23:00:00 EST 1986 · OSTI ID:5792749