skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Actinide processing for ATW

Conference ·
OSTI ID:141193
 [1]
  1. Los Alamos National Laboratory, NM (United States)

A baseline flow sheet for chemical processing of actinide and fission product materials has been developed. Because of the need to keep the actinide concentrations constant and the fission product concentrations low for efficient transmutation and to minimize the actinide inventory in storage after transmutation, it is necessary to process the material within the blanket soon after discharge from the transmuter. The high-radiation and thermal load from the irradiated material places severe constraints on the processes that can be used. After dissolution in nitric acid, a radiation-stable and selective liquid anion exchanger (Aliquat 336) is proposed to separate neptunium, plutonium, technetium, and palladium from the bulk of the process stream. A reverse-TALSPEAK process employing a liquid cation exchanger (di-2-ethylhexylphosphoric acid) will separate the trivalent actinides from the remaining fission products. The proposed processes were chosen as the baseline because they have been successfully tested with high-level radioactive wastes or fuels in gram to kilogram quantities. Less tested but potentially improved processing steps are discussed as advanced options relative to the baseline case.

OSTI ID:
141193
Report Number(s):
CONF-930304-; TRN: 93:003688-0868
Resource Relation:
Conference: 205. American Chemical Society national meeting, Denver, CO (United States), 28 Mar - 2 Apr 1993; Other Information: PBD: 1993; Related Information: Is Part Of 205th ACS national meeting; PB: 1951 p.
Country of Publication:
United States
Language:
English