About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
|
Symposium
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Materials and Chemistry for Molten Salt Systems
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Presentation Title |
Synthesis of Actinide Fluorides and Chlorides for Molten Salt Reactor Fuels |
Author(s) |
Pavel Soucek, O. Beneš, M. Fucina, E. Capelli, P.R. Hania, E. D'Agata, A. Rodrigues, H.J. Uitslag-Doolaard, R. Konings |
On-Site Speaker (Planned) |
Pavel Soucek |
Abstract Scope |
Pure actinide fluorides and chlorides are essential materials for the experimental measurements of thermodynamic and physico-chemical properties of any Molten Salt Reactor (MSR) fuel. This work is focused on synthesis, purification and characterisation of pure ThF4, UF4, UF3, PuF3, UCl4 and PuCl3, as typical fissile or fertile materials for the MSR fuels. The experimental set-up using pure HF, Cl2 and HCl gases is mentioned, as well as the methods and analytical scheme developed for the syntheses. In addition, the fabrication of molten salt fuels in 100g-scale for the irradiation experiments SALIENT-01 and -03 is described. These projects are carried out within collaboration between the Nuclear Research and Consultancy Group (The Netherlands) and Joint Research Centre (European Commission). The main goals of the experiments are to assess the behaviour of the molten fuels containing ThF4, UF4, UF3 and PuF3 during irradiation and the corrosion test of selected Ni-based alloys. |
Proceedings Inclusion? |
Planned: |