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Pyrochemical reprocessing of molten salt fast reactor fuel: focus on the reductive extraction step

100%

Rodrigues D., Durán-Klie G., Delpech S.

issue 4

907-914

The nuclear fuel reprocessing is a prerequisite for nuclear energy to be a clean and sustainable energy. In the case of the molten salt reactor containing a liquid fuel, pyrometallurgical way is an obvious way. The method for treatment of the liquid fuel is divided into two parts. In-situ injection of helium gas into the fuel leads to extract the gaseous fission products and a part of the noble metals. The second part of the reprocessing is performed by ‘batch’. It aims to recover the fissile material and to separate the minor actinides from fission products. The reprocessing involves several chemical steps based on redox and acido-basic properties of the various elements contained in the fuel salt. One challenge is to perform a selective extraction of actinides and lanthanides in spent liquid fuel. Extraction of actinides and lanthanides are successively performed by a reductive extraction in liquid bismuth pool containing metallic lithium as a reductive reagent. The objective of this paper is to give a description of the several steps of the reprocessing retained for the molten salt fast reactor (MSFR) concept and to present the initial results obtained for the reductive extraction experiments realized in static conditions by contacting LiF-ThF4-UF4-NdF3 with a lab-made Bi-Li pool and for which extraction efficiencies of 0.7% for neodymium and 14.0% for uranium were measured. It was concluded that in static conditions, the extraction is governed by a kinetic limitation and not by the thermodynamic equilibrium.

Uranium and neodymium partitioning in alkali chloride melts using low-melting gallium-based alloys

75%

Melchakov S. Y., Maltsev D. S., Volkovich V. A., Yamshchikov L. F., Lisienko D. G., Osipenko A. G., Rusakov M. A.

issue 4

915-920

Partitioning of uranium and neodymium was studied in a ‘molten chloride salt - liquid Ga-X (X = In or Sn) alloy’ system. Chloride melts were based on the low-melting ternary LiCl-KCl-CsCl eutectic. Nd/U separation factors were calculated from the thermodynamic data as well as determined experimentally. Separation of uranium and neodymium was studied using reductive extraction with neodymium acting as a reducing agent. Efficient partitioning of lanthanides (Nd) and actinides (U), simulating fission products and fissile materials in irradiated nuclear fuels, was achieved in a single stage process. The experimentally observed Nd/U separation factor valued up to 106, depending on the conditions.

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2 Nukleonika

2 2015

1 Delpech S.

1 Durán-Klie G.

1 Lisienko D. G.

1 Maltsev D. S.

1 Melchakov S. Y.

1 Osipenko A. G.

1 Rodrigues D.

1 Rusakov M. A.

1 Volkovich V. A.

1 Yamshchikov L. F.

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Pyrochemical reprocessing of molten salt fast reactor fuel: focus on the reductive extraction step

Uranium and neodymium partitioning in alkali chloride melts using low-melting gallium-based alloys