A HELIOS-Based Dynamic Salt Clean-Up Study for iMAGINE
Source abstract
Abstract
Nuclear technologies have the potential to play a unique role in delivering low carbon energy for a future net-zero society. However, for long-term success, nuclear technologies will need to deliver innovative solutions as proposed in iMAGINE. One of the key challenges for the envisaged highly integrated nuclear energy system is the need for a demand-driven salt clean-up system. The work described provides an insight into the interplay between a potential salt clean-up system and the reactor operation in a dynamic approach. The results provided will help to optimise the parameters for the salt clean-up process by delivering a dynamically calculated priority list, identifying the elements with great influence on reactor operation. The integrated model is used to investigate the ideal time for the initiation of the clean-up as well as the effect of different throughputs through the clean-up system on criticality as well as on the concentration of the elements in the reactor salt. Finally, a staggered approach is proposed with the idea to phase in the chemical clean-up processes step by step to keep the reactor critical. The results provide an essential step for the progress of iMAGINE as well as a basis for the interdisciplinary work required to bring iMAGINE into real operation.
Source: crossref · Quality: baseline
Research context
OpenAlex topics: Nuclear reactor physics and engineering · Graphite, nuclear technology, radiation studies · Nuclear Materials and Properties
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
Affiliations
School of Engineering, The University of Liverpool, Liverpool L69 3GH, UK
STFC Daresbury Laboratory, Daresbury, Warrington WA4 4AD, UK
Funding
The Royal Academy of Engineering
References (33)
Show source-provided references
1. (2022, July 06). Profiling the Top Nuclear Power Pros and Cons, NS-Energy Business. Available online: https://www.nsenergybusiness.com/features/newstop-nuclear-power-pros-and-cons-5760814/.
2. Progress in reliability of fast reactor operation and new trends to increased inherent safety10.1016/j.apenergy.2015.02.023 ↗
3. Merk, B., Litskevich, D., Bankhead, M., and Taylor, R.J. (2017). An innovative way of thinking nuclear waste management—Neutron physics of a reactor directly operating on SNF. PLoS ONE, 12.10.1371/journal.pone.0180703 ↗
4. On a Long Term Strategy for the Success of Nuclear Power10.3390/en81112328 ↗
5. The Current Status of Partitioning & Transmutation and How to Develop an Innovative Approach to Nuclear Waste Management
6. iMAGINE—A disruptive change to nuclear or how can we make more out of the existing spent nuclear fuel and what has to be done to make it possible in the UK?
7. Salvatores, M. (2022, July 06). Advanced Options for Transmutation Strategies. Available online: https://core.ac.uk/reader/21748160.
8. Experience with the Molten-Salt Reactor Experiment
9. Taube, M. (2022, March 08). Fast Reactors Using Molten Chloride Salts as Fuel Final Report (1972–1977). Available online: https://inis.iaea.org/collection/NCLCollectionStore/_Public/13/648/13648304.pdf.
10. Chemistry and technology of Molten Salt Reactors—History and perspectives10.1016/j.jnucmat.2006.08.008 ↗
11. Pyrochemical reprocessing of molten salt fast reactor fuel: Focus on the reductive extraction step10.1515/nuka-2015-0153 ↗
12. (2022, March 08). Evol (Project n. 249696) Final Report. Available online: https://cordis.europa.eu/docs/results/249/249696/final1-final-report-f.pdf.
13. Mcfarlane, J., Ezell, N.D.B., Del Cul, G., Holcomb, D., Myhre, K., Lines, A., Bryan, S., Felmy, H.M., Riley, B., and Chapel, A. (2022, March 08). Fission Product Volatility and Off-Gas Systems for Molten Salt Reactors, ORNL/TM-2019/1266, Available online: https://info.ornl.gov/sites/publications/Files/Pub129748.pdf.10.2172/1560441 ↗
14. Review of molten salt reactor off-gas management considerations10.1016/j.nucengdes.2021.111529 ↗
15. Merk, B., Litskevich, D., Gregg, R., and Mount, A.R. (2018). Demand driven salt clean-up in a molten salt fast reactor–Defining a priority list. PLoS ONE, 13.10.1371/journal.pone.0192020 ↗
16. Merk, B., Detkina, A., Litskevich, D., Drury, M., Noori-kalkhoran, O., Cartland-Glover, G., Petit, L., Rolfo, S., Elliott, J.P., and Mount, A.R. (2022). Defining the Challenges—Identifying the Key Poisoning Elements to Be Separated in a Future Integrated Molten Salt Fast Reactor Clean-Up System for iMAGINE. Appl. Sci., 12.10.20944/preprints202202.0148.v1 ↗
17. Merk, B., and Litskevich, D. (2015). Transmutation of All German Transuranium under Nuclear Phase out Conditions-Is This Feasible from Neutronic Point of View?. PLoS ONE, 10.10.1371/journal.pone.0145652 ↗
18. Merk, B., Rohde, U., Glivici-Cotruta, V., Litskevich, D., and Scholl, S. (2014). On the Use of a Molten Salt Fast Reactor to Apply an Idealized Transmutation Scenario for the Nuclear Phase Out. PLoS ONE, 9.10.1371/journal.pone.0092776 ↗
19. An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor10.1016/j.jnucmat.2013.06.026 ↗
20. Modeling and criticality calculation of the Molten Salt Fast Reactor using Serpent code10.1088/1742-6596/1189/1/012007 ↗
21. HELIOS2 Methods Manual (version 2.03.01), Studsvik, SSP-11/452 revised 6, 12 January 2021.
22. HELIOS: Angularly dependent collision probabilities10.13182/NSE112-16 ↗
23. Wemple, C.A., Gheorghiu, H.-N.M., Stamm’ler, R.J.J., and Villarino, E.A. (2008, January 14–19). Recent Advances in the HELIOS-2 Lattice Physics Code. Proceedings of the International Conference on the Physics of Reactors “Nuclear Power: A Sustainable Resource”, Interlaken, Switzerland.
24. (2022, July 30). Evaluation and Viability of Liquid Fuel Fast Reactor System EVOL, DELIVERABLE D2.1, Design parameters definition for most stable salt flux, rev 3 30/04/2012. Available online: https://cordis.europa.eu/project/id/249696/results.
25. Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects10.1051/epjn/2018052 ↗
26. Merk, B., Detkina, A., Atkinson, S., Litskevich, D., and Catland-Glover, G. (2019). Evaluation of the Breeding Performance of a NaCl-UCl-Based Reactor System. Energies, 12.10.3390/en12203853 ↗
27. Merk, B., Detkina, A., Litskevich, D., Atkinson, S., and Cartland-Glover, G. (2020). The Interplay between Breeding and Thermal Feedback in a Molten Chlorine Fast Reactor. Energies, 13.10.3390/en13071609 ↗
28. Rearden, B.T., and Jessee, M.A. (2017). POLARIS-2D light water reactor lattice physics module. SCALE Code System, National Laboratory.10.2172/1408010 ↗
29. AURORA USER MANUAL, Studsvik, SSP-11/451 Rev 8, 12 January 2021.
30. ZENITH USER MANUAL, Studsvik, SSP-11/460 Rev. 5, 8 December 2020.
31. Neutronic analysis of SFR core with HELIOS-2, Serpent, and DYN3D codes10.1016/j.anucene.2012.11.030 ↗
32. Detkina, A., Litskevich, D., Drury, M., and Merk, B. (2022, January 15–20). Zero Power Experiment for Molten Salt Reactor—Code Verification and Validation Request. Proceedings of the International Conference on Physics of Reactors, Pittsburgh, PA, USA.10.13182/PHYSOR22-37633 ↗
33. (2022, July 26). A Decision on the Fate of UK’s Plutonium Stockpile Remains Years Away. Available online: http://corecumbria.co.uk/briefings/a-decision-on-the-fate-of-uks-plutonium-stockpile-remains-years-away/.