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Title: Separation of technetium and rare earth metals for co-decontamination process

Poster. In the US there are several technologies under consideration for the separation of the useful components in used nuclear fuel. One such process is the co-decontamination process to separate U, Np and Pu in a single step and produce a Np/ Pu and a U product stream. Although the behavior of the actinide elements is reasonably well defined in this system, the same is not true for the fission products, mainly Zr, Mo, Ru and Tc. As these elements are cationic and anionic they may interact with each other to extract in a manner not predicted by empirical models such as AMUSE. This poster presentation will discuss the initial results of batch contact testing under flowsheet conditions and as a function of varying acidity and flowsheet conditions to optimize recovery of Tc and minimize extraction of Mo, Zr and Ru with the goal of developing a better understanding of the behavior of these elements in the co-decontamination process.
Authors:
;
Publication Date:
OSTI Identifier:
1186761
Report Number(s):
INL/CON--15-35267
TRN: US1500174
DOE Contract Number:
AC07-05ID14517
Resource Type:
Conference
Resource Relation:
Conference: 39. Actinide Separations Conference, Salt Lake City, UT (United States), 18-21 May 2015
Research Org:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY; TECHNETIUM; RARE EARTHS; MATERIALS RECOVERY; FISSION PRODUCTS; PH VALUE; TESTING; SPENT FUELS; REPROCESSING; CHEMICAL REACTIONS fission products; separations; Technetium; Uranium