A HELIOS-Based Dynamic Salt Clean-Up Study Analysing the Effects of a Plutonium-Based Initial Core for iMAGINE

Bruno Merk (), Anna Detkina, Dzianis Litskevich, Omid Noori-kalkhoran, Lakshay Jain and Gregory Cartland-Glover
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Bruno Merk: School of Engineering, The University of Liverpool, Liverpool L69 3GH, UK
Anna Detkina: School of Engineering, The University of Liverpool, Liverpool L69 3GH, UK
Dzianis Litskevich: School of Engineering, The University of Liverpool, Liverpool L69 3GH, UK
Omid Noori-kalkhoran: School of Engineering, The University of Liverpool, Liverpool L69 3GH, UK
Lakshay Jain: School of Engineering, The University of Liverpool, Liverpool L69 3GH, UK
Gregory Cartland-Glover: STFC Daresbury Laboratory, Daresbury WA4 4AD, UK

Energies, 2022, vol. 15, issue 24, 1-17

Abstract: Nuclear technologies have strong potential and a unique role to play in delivering reliable low carbon energy to enable a net-zero society for future generations. However, to assure the sustainability required for its long-term success, nuclear will need to deliver innovative solutions as proposed in iMAGINE. One of the most attractive features, but also a key challenge for the envisaged highly integrated nuclear energy system iMAGINE, is the need for a demand driven salt clean-up system based on the principles of reverse reprocessing. The work described provides an insight into the dynamic interplay between a potential salt clean-up system and reactor operation in a plutonium-started core in a dynamic approach. The results presented will help to optimise the parameters for the salt clean-up process as well as to understand the differences which appear between a core started with enriched uranium and plutonium as the fissile material. The integrated model is used to investigate the effects of the initial fissile material on core size, achievable burnup, and long-term operation. Different approaches are tested to achieve a higher burnup in the significantly smaller Pu-driven core. The effects of different clean-up system throughputs on the concentration of fission products in the reactor salt and its consequences are discussed for general molten salt reactor design. Finally, an investigation into how a plutonium loaded core could be used to provide fuel for future reactors through fuel salt splitting is presented, with the outcome that one Pu-started reactor of the same size as a uranium-started core could deliver fuel for 1.5 new cores due to enhanced breeding. The results provide an essential understanding for the progress of iMAGINE as well as the basis for inter-disciplinary work required for optimising iMAGINE.

Keywords: nuclear; nuclear energy; nuclear reactors; reactor physics; modelling and simulation; molten salt reactors; nuclear chemistry; fission products; salt clean-up; plutonium management (search for similar items in EconPapers)
JEL-codes: Q Q0 Q4 Q40 Q41 Q42 Q43 Q47 Q48 Q49 (search for similar items in EconPapers)
Date: 2022
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