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

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.

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

International Journal of PIXE ◽

10.1142/s0129083517500012 ◽

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.

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Assessment of fission product content of high-level liquid waste supernate on E-Area vault package criteria

10.2172/10185969 ◽

1994 ◽

Author(s):

D.F. Brown

Keyword(s):

Fission Product ◽

Liquid Waste ◽

High Level Liquid Waste ◽

High Level

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

Nuclear Science and Techniques ◽

10.1007/s41365-017-0327-3 ◽

2017 ◽

Vol 28 (12) ◽

Cited By ~ 5

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

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Adsorption Materials Development for the Separation of Actinides and Specific Fission Products from High Level Waste

Advances in Science and Technology ◽

10.4028/www.scientific.net/ast.94.103 ◽

2014 ◽

Vol 94 ◽

pp. 103-110 ◽

Cited By ~ 3

Author(s):

Yue Zhou Wei ◽

Shun Yan Ning ◽

Qi Long Wang ◽

Zi Chen ◽

Yan Wu ◽

...

Keyword(s):

Spent Nuclear Fuel ◽

Selective Adsorption ◽

Packed Column ◽

Liquid Waste ◽

Separation Method ◽

High Level Waste ◽

Small Scale ◽

Fast Diffusion ◽

High Level Liquid Waste ◽

High Level

The long-term radiotoxicity of high level liquid waste (HLLW) generated in spent nuclear fuel reprocessing is governed by the content of several long-lived minor actinides (MA) and some specific fission product nuclides. To efficiently separate MA (Am, Cm) and some FPs such as Cs and Sr from the HLLW, we have been studying an advanced aqueous partitioning process, which uses selective adsorption as separation method. In this work, we prepared different types of porous silica-based organic/inorganic adsorbents with fast diffusion kinetics, improved chemical stability and low pressure drop in a packed column. So they are advantageously applicable to efficient separation of the MA and specific FP elements from HLLW. Adsorption and separation behaviors of the MA and some FP elements such as Cs and Sr were studied. Small scale separation tests using simulated and genuine nuclear waste solutions were carried out and the obtained results indicate that the proposed separation method based on selective adsorption is essentially feasible.

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Radiocesium removal from high level liquid waste and immobilisation in sodium silicotitanate for geological disposal

Radiochimica Acta ◽

10.1524/ract.2001.89.3.145 ◽

2001 ◽

Vol 89 (3) ◽

Cited By ~ 7

Author(s):

T. Tomasberger ◽

A.C. Veltkamp ◽

A. S. Booij ◽

U. W. Scherer

Keyword(s):

Ion Exchange ◽

Fission Product ◽

Liquid Waste ◽

High Level Liquid Waste ◽

Geological Disposal ◽

Inorganic Ion ◽

Exchange Material ◽

Leaching Behaviour ◽

Concentration Factors ◽

High Level

The isolation of the fission product cesium from high-level alkaline liquid waste is studied with inorganic ion-exchange materials. High separation and concentration factors can be obtained using sodium silicotitanate (CST). The leaching behaviour of cesium from CST was studied in clay porewater and Quinary brine at 90 °C. It is shown that cesium leaching in Quinary brine can be drastically reduced by thermal treatment of cesium loaded CST above 1000 °C. To this end, neutralisation of the ion exchange material before heating is required in order to reduce cesium volatility. It is concluded that CST is a good candidate material for geological disposal of the fission product cesium.

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