Extraction chromatography–electrodeposition (EC–ED) process to recover palladium from high-level liquid waste

2017 ◽  
Vol 28 (12) ◽  
Author(s):  
Qing Zou ◽  
Shuai Gu ◽  
Rui-Qin Liu ◽  
Shun-Yan Ning ◽  
Yan-Liang Chen ◽  
...  
Keyword(s):  
Extraction Chromatography ◽  
Liquid Waste ◽  
High Level Liquid Waste ◽  
High Level

scholarly journals Micro-PIXE analysis on adsorbent of extraction chromatography for MA(III) recovery

2016 ◽  
Vol 26 (03n04) ◽  
pp. 73-83
Author(s):  
Y. Takahatake ◽  
S. Watanabe ◽  
H. Kofuji ◽  
M. Takeuchi ◽  
K. Nomura ◽  
...  
Keyword(s):  
Extraction Chromatography ◽  
Packed Column ◽  
Liquid Waste ◽  
Flow Sheet ◽  
Simple Experiment ◽  
High Level Liquid Waste ◽  
Energy Agency ◽  
Pixe Analysis ◽  
Conducting Research ◽  
High Level

Japan Atomic Energy Agency (JAEA) has been conducting research and development of MA(III) recovery from high level liquid waste (HLLW) by extraction chromatography technology for reduction in amount and environmental impact of radioactive waste. The behavior of adsorbed cations inside the adsorbent packed in a column is necessary to be evaluated for improvement of the adsorbent or flow-sheet to achieve targeted MA(III) recovery performance. In this paper, micro-PIXE analysis was carried out on the particles sampled from various positions of the column to reveal the behavior of cations inside the packed column with CMPO/SiO2-P adsorbent using RE(III) as simulated elements of MA(III). Simple experiment and data analysis were shown to be effective to reveal inside of the column, and formation and transportation of the adsorption bands were observed for some cations which are extractable by the CMPO extractant. Some part of Zr(IV) and Mo(VI) were found to remain inside the column without distinct transportation even after the elution operation. Those results will contribute to design more practical MA(III) recovery flow-sheet.

scholarly journals Development of MA separation process with TEHDGA/SiO2-P for an advanced reprocessing

2021 ◽  
Vol 330 (1) ◽  
pp. 237-244
Author(s):  
Yusuke Horiuchi ◽  
Sou Watanabe ◽  
Yuichi Sano ◽  
Masayuki Takeuchi ◽  
Fukuka Kida ◽  
...  
Keyword(s):  
Fission Product ◽  
Distribution Ratio ◽  
Extraction Chromatography ◽  
Packed Column ◽  
Liquid Waste ◽  
Separation Process ◽  
Minor Actinide ◽  
High Level Liquid Waste ◽  
Column Separation ◽  
High Level

AbstractApplicability of tetra2-ehylhexyl diglycolamide (TEHDGA) impregnated adsorbent for minor actinide (MA) recovery from high level liquid waste (HLLW) in extraction chromatography technology was investigated through batch-wise adsorption and column separation experiments. Distribution ratio of representative fission product elements were obtained by the batch-wise experiments, and TEHDGA adsorbent was shown to be preferable to TODGA adsorbent for decontamination of several species. All Ln(III) supplied into the TEHDGA adsorbent packed column was properly eluted from the column, and the applicability of the adsorbent was successfully showed by this study.

scholarly journals Vitrification of HLW Produced by Uranium/Molybdenum Fuel Reprocessing in COGEMA’s Cold Crucible Melter

2003 ◽  
Author(s):  
R. Do Quang ◽  
V. Petitjean ◽  
F. Hollebecque ◽  
O. Pinet ◽  
T. Flament ◽  
...  
Keyword(s):  
Atomic Energy Commission ◽  
Liquid Waste ◽  
Glass Layer ◽  
Cold Crucible ◽  
High Level Liquid Waste ◽  
Process Waste ◽  
Glass Formulation ◽  
High Level ◽  
Fuel Reprocessing ◽  
High Frequency Induction

The performance of the vitrification process currently used in the La Hague commercial reprocessing plants has been continuously improved during more than ten years of operation. In parallel COGEMA (industrial Operator), the French Atomic Energy Commission (CEA) and SGN (respectively COGEMA’s R&D provider and Engineering) have developed the cold crucible melter vitrification technology to obtain greater operating flexibility, increased plant availability and further reduction of secondary waste generated during operations. The cold crucible is a compact water-cooled melter in which the radioactive waste and the glass additives are melted by direct high frequency induction. The cooling of the melter produces a soldified glass layer that protects the melter’s inner wall from corrosion. Because the heat is transferred directly to the melt, high operating temperatures can be achieved with no impact on the melter itself. COGEMA plans to implement the cold crucible technology to vitrify high level liquid waste from reprocessed spent U-Mo-Sn-Al fuel (used in gas cooled reactor). The cold crucible was selected for the vitrification of this particularly hard-to-process waste stream because it could not be reasonably processed in the standard hot induction melters currently used at the La Hague vitrification facilities: the waste has a high molybdenum content which makes it very corrosive and also requires a special high temperature glass formulation to obtain sufficiently high waste loading factors (12% in molybednum). A special glass formulation has been developed by the CEA and has been qualified through lab and pilot testing to meet standard waste acceptance criteria for final disposal of the U-Mo waste. The process and the associated technologies have been also being qualified on a full-scale prototype at the CEA pilot facility in Marcoule. Engineering study has been integrated in parallel in order to take into account that the Cold Crucible should be installed remotely in one of the R7 vitrification cell. This paper will present the results obtained in the framework of these qualification programs.

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