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Conference Papers Year : 2016

Uranium - plutonium separation trials from spent nuclear fuel in CBP shielded cell

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1

Abstract

In the framework of the development of Generation IV reactors, innovative solvent extraction (SX) processes are under development for the reprocessing of spent nuclear fuels. Monoamides demonstrated their potentiality in the recovery and recycling of fissile materials, plutonium and uranium, as an alternative to TBP. First, they exhibit a good stability towards radiolysis and hydrolysis. Secondly, distribution ratios of Pu(IV) and U(VI) with monoamides are such that their extraction and separation is possible, without using any reducing agent for the uranium plutonium partitioning.To validate these potentialities, the CBP shielded cell is a unique facility to conduct all operations from the reception of spent fuel to the demonstrative pilot tests on genuine High Liquid Wastes (HLW). CBP hot cell docking equipments allow the reception of both LWR and FNR spent fuels transported either by RD15IIB, TN106 or more recently by IR100. HLW is obtained after batch dissolution of spent fuels operated in 8 to 16 litres dissolver. Solvent extraction processes can then be validated during trials conducted either in mixer-settlers banks or in pulsed columns. Mixer-settlers batteries are operated to demonstrate scientific feasibility of the SX process while pulsed columns are used to assess the technical feasibility. CBP shielded cell is indeed the world unique RandD hot cell allowing the operation of four meter high pulsed columns with HLW. In addition to these devices, the monitoring of experimental concentration is conducted by coupling in-line measurements (pH, temperature, spectrophotometry..) and deported analysis performed in the analytical hot cell CBA which is connected via a pneumatic transport line.
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Dates and versions

cea-02509789 , version 1 (17-03-2020)

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  • HAL Id : cea-02509789 , version 1

Cite

C. Sorel, F. Antegnard, M.-J. Bollesteros, S. Costenoble, M. Montuir, et al.. Uranium - plutonium separation trials from spent nuclear fuel in CBP shielded cell. 5th ATALANTE 2016 – Nuclear Chemistry for Sustainable Fuel Cycles, Jun 2016, Montpellier, France. ⟨cea-02509789⟩

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