Thorium—Energy for the Future pp 117-124 | Cite as
Technology Assessment of Near-Term Open-Cycle Thorium-Fuelled Nuclear Energy Systems
Abstract
As part of the RCUK–India civil nuclear research collaboration, British and Indian researchers have assessed the merits and disadvantages of, and potential for, open-cycle thorium–uranium-fuelled (Th–U-fuelled) nuclear energy systems. The research centred on fuel cycle modelling and life-cycle assessment of three Th–U-fuelled nuclear energy systems and compared these to a reference uranium-fuelled nuclear energy system, all operating with open nuclear fuel cycles. The results indicate that thorium-based fuels offer little benefit over conventional uranium-fuelled approaches for open-cycle nuclear energy production. This chapter provides an overview on the project and stresses overarching conclusions.
Keywords
Thorium Nuclear fuel cycle Life-cycle analysis Technology assessmentNomenclature
- ADSR
Accelerator-driven subcritical reactor
- AHWR
Advanced heavy water reactor (DAE India funded)
- CANDU
A widely adopted type of pressurised heavy water reactor developed in Canada
- EPR
European pressurised reactor (AREVA)
- FC
Fuel cycle
- GHG
Greenhouse gas
- GT-MHR
Gas turbine modular helium reactor (General Atomics)
- LCA
Life-cycle analysis
- LCOE
Levelised cost of electricity
- MOX
Mixed oxide (nuclear fuel)
- MSR
Molten salt reactor (various concepts)
- PR
Proliferation resistance
- PWR
Pressurised water reactor
- SNF
Spent nuclear fuel
Notes
Acknowledgements
The work was funded by the Engineering and Physical Sciences Research Council (UK) under grant no. EP/I018425/1. We are most grateful to all those who worked to establish the RCUK–India civil nuclear collaboration. We also wish to note our gratitude to all those listed as co-authors and in the acknowledgements sections of the papers where our individual studies are more fully described.
References
- 1.S.F. Ashley, R.A. Fenner, W.J. Nuttall, G.T. Parks, Open cycle thorium–uranium-fuelled nuclear energy systems. Proc. ICE Energy 166(2), 74–81 (2013)Google Scholar
- 2.R. Gregg, C. Grove, Analysis of the UK nuclear fission roadmap using the ORION fuel cycle modelling code, in Proceedings of IChemE Nuclear Fuel Cycle Conference, IChemE, Manchester, UK, 2012Google Scholar
- 3.S.F. Ashley, B.A. Lindley, G.T. Parks, W.J. Nuttall, R. Gregg, K.W. Hesketh, U. Kannan, P.D. Krishnani, B. Singh, A. Thakur, M. Cowper, A. Talamo, Fuel cycle modelling of open cycle thorium-fuelled nuclear energy systems. Ann. Nucl. Energy 69, 314–330 (2014)CrossRefGoogle Scholar
- 4.S.F. Ashley, R.A. Fenner, W.J. Nuttall, G.T. Parks, Life-cycle impacts from novel thorium–uranium-fuelled nuclear energy systems. Energy Convers. Manag. 101, 136–150 (2015)CrossRefGoogle Scholar
- 5.S.F. Ashley, W.J. Nuttall, G.T. Parks, A. Worrall, On the proliferation resistance of thorium–uranium nuclear fuel, in Proceedings of UK PONI Conference, 2012Google Scholar
- 6.S.J. Steer, W.J. Nuttall, G.T. Parks, L.V.N. Gonçalves, Predicting the contractual cost of unplanned shutdowns of power stations: an accelerator-driven subcritical reactor case study. Electr. Power Syst. Res. 81, 1662–1671 (2011)CrossRefGoogle Scholar
- 7.CANDU Energy, EC6 and the CANMOX Project, corporate brochure available at: http://www.candu.com/site/media/Parent/CANDU%20brochure-CANMOX-0905.pdf no date
- 8.E. Shwageraus, H. Feinroth, Potential of silicon carbide cladding to extend burnup of Pu-Th mixed oxide fuel, in Proceedings of American Nuclear Society (ANS) Annual Meeting, Hollywood, Florida, USA, pp. 658–660, 2011Google Scholar
- 9.B.A. Lindley, C. Fiorina, F. Franceschini, E.J. Lahoda, G.T. Parks, Thorium breeder and burner fuel cycles in reduced-moderation LWRs compared to fast reactors. Prog. Nucl. Energy 77, 107–123 (2014)CrossRefGoogle Scholar