Neutronic Assessment of High-Temperature Gas-Cooled Thorium Burner using Monte Carlo Calculation Method with Full Core Model

Abstract

In this study, the effective reactivity and burnup analyses have been performed for heterogeneous three-dimensional high-temperature gas-cooled thorium reactor (HTGR) which has 60 MWth full core geometry by using continuous-energy multi-purpose three-dimensional Monte Carlo particle transport Serpent code with ENDF/ B-VII data libraries. Nuclear fuel have been selected as 50 % ThO2+50% RG-PuO2. Firstly, effective reactivity for three different qualities of graphite for operation period have been determined. The effective reactivity showed better performance with increasing densities of graphite. Secondly, it has been also examined to ZrC and SiC cladding materials effect on the effective reactivity. It is observed that SiC has a positive effect on reactivity compared to ZrC. As a results, the full core life low-power thorium-burner HTGR have been calculated as up to ~4500 days depending on the graphite material whereas, the corresponding burn−ups came out to be ~ 189 GWd/ton, for end of life.

Keywords

• Monte Carlo
• HTGR
• Reactivity
• Burnup analysis
• Graphite

References

1. 1. IAEA, (2003), Potential of Thorium Based Fuel Cycles to Constrain Plutonium and Reduce Long Lived Waste Toxicity, IAEA-TECDOC-1349, International Atomic Energy Agency.
2. 2. Şahin, S., Yıldız, K., Acır, A., (2004a), Power Flattening in the Fuel Bundle of a CANDU Reactor, Nuclear Engineering and Design, 232(1): 7 – 18.
3. 3. Şahin, S., K. Yıldız, H. M. Şahin, A. Acır (2006a), “Investigation of CANDU Reactors as a Thorium Burner”, Energy Conversion and Management, Vol. 47, nos. 13 - 14, pp. 1661 – 1675.
4. 4. Sahin, S; Sahin, HM and Acir, A. (2010). Utilization of TRISO fuel with reactor grade plutonium in CANDU reactors, 240 (8) , pp.2066-2074.
5. 5. Sahin, S; Sahin, HM and Acir, A. (2010). Criticality and burn up evolutions of the Fixed Bed Nuclear Reactor with alternative fuels, Energy Conversion and Management, 51 (9) , pp.1781-1787
6. 6. Acir, A and Coskun, H (2012). Neutronic analysis of the PBMR-400 full core using thorium fuel mixed with plutonium or minor actinides, Annals of Nuclear Energy, 48 , 45-50
7. 7. Mohamed A. Alzamly, Moustafa Aziz, Alya A. Badawi, Hana Abou Gabal, Abdel Rraouf A. Gadallah (2020). Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide, Nuclear Engineering and Technology, 52, 4, 674-680.
8. 8. I.V. Shamanin (2018). Neutronic7 properties of high-temperature gas-cooled reactors with thorium fuel. Annals of Nuclear Energy, 113, 286–293.

9. 9. I.V. Shamanin (2015). Gas-cooled thorium reactor with fuel block of the unified design. Nuclear Energy and Technology 1, (2015), 184-190.
10. 10. Petti, D.A., Hobbins, R.R., Lowry, P., Gougar, H., (2013). Representative Source terms and the influence of reactor attributes on functional containment in modular high-temperature gas-cooled reactors. Nucl. Technol. 184, 181–197.
11. 11. Rowinski, M.K., White, T.J., Zhao, J., (2015). Small and Medium sized Reactors: a review of technology. Renew. Sust. Energy Rev. 44, 643–656.
12. 12. Black, G., Black, M.A.T., Solan, D., et al., (2015). Carbon free energy development and the role of small modular reactors: a review and decision framework for deployment in developing countries. Renew. Sust. Energy Rev. 43, 83–94.
13. 13. T. Koyanagi, Y. Katoh, G. Singh M. Snead. (2017) SiC/SiC Cladding Materials Properties Handbook. Nuclear Technology Research and Development.
14. 14. H. C. No (2007). A Review of helium gas turbine technology for high-temperature gas-cooled reactors. Nuclear Energy and Technology, 39 (1), 21-30.
15. 15. J. Leppänen, (2015) “Serpent – a Continuous-energy Monte Carlo Reactor Physics Burnup Calculation Code”, VTT Technical Research Centre of Finland.
16. 16. Lamarsh, J.R., Baratta, A.J., (2001). Introduction to nuclear engineering, vol. 3. Prentice Hall, Upper Saddle River, NJ.
17. 17. Moniz, E. (2011). Why we still need nuclear power: making clean energy safe and affordable. Foreign Affairs, 83-94.
18. 18. https://www.ucsusa.org/resources/small-modular-reactors (Erişim Tarihi: 03:06:2023)
19. 19. Stauff, N. E., Lee, C. H., Shriwise, P., Wells, A., & Filippone, C. (2021). Neutronic Benchmark on Holos-Quad Micro-Reactor Concept. In EPJ Web of Conferences (Vol. 247, p. 01006). EDP Sciences.