Published 1996 | Version v1
Report Open

Progress in dissolving modified LEU Cintichem targets

  • 1. Argonne National Lab., IL (United States). Chemical Technology Div.

Description

A process is under development to use low-enriched uranium (LEU) metal targets for production of 99Mo. The first step is to dissolve the irradiated foil. In past work, this has been done by heating a closed (sealed) vessel containing the foil and a solution of nitric and sulfuric acids. In this work, the authors have demonstrated that (1) the dissolver solution can contain nitric acid alone, (2) uranium dioxide is also dissolved by nitric acid alone, and (3) barrier metals of Cu, Fe, or Ni on the U foil are also dissolved by nitric acid. Changes to the dissolver design and operation needed to accommodate the uranium foil are discussed, including (1) simple operations that are easy to do in a remote-maintenance facility, (2) heat removal from the irradiated LEU foil, and (3) cold trap operation with high dissolver pressures

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE97000398; NTIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
31 p.
Report number
ANL--CMT/CP-91323

Conference

Title
19. international meeting on reduced enrichment for research and test reactors (RERTR).
Dates
7-10 Oct 1996.
Place
Seoul (Korea, Republic of).

Optional Information

Contract/Grant/Project number
Contract W-31109-ENG-38
Funding organization
USDOE, Washington, DC (United States).
Secondary number(s)
ANL/CMT/VU--91323; CONF-9610205--9.