Evaluation of thorium-based fuels for 12-year operation of small modular BWR without refueling

Authors

DOI:

https://doi.org/10.15587/1729-4061.2025.335730

Keywords:

thorium fuel, extended fuel cycle, neutronic performance, 233U, Keff, burnup level, power density distribution, PPF

Abstract

The object of this study is an 870 MW small modular boiling water reactor (SMR-BWR) core that is expected to operate for 12 years without refueling. The main issue addressed is conventional BWR designs' limited fuel cycle duration, typically requiring refueling every 2–3 years. This short refueling period increases operational costs, leads to more extended maintenance downtimes, and generates larger volumes of spent fuel waste. This study examines the neutronic performance of thorium-based fuels, namely (Th-235U)O2 and (Th-233U)O2, and compares them with standard UO2 fuel in an SMR-BWR core configuration. The reactor core is a heterogeneous core consisting of 3 fuel zones. To control reactivity, a burnable poison in the form of B4C is also added to the fuel. Neutronic calculations are performed using the standard reactor analysis code (SRAC) system with the JENDL-4.0 nuclear data library. The SRAC code uses the PIJ module for fuel cell level calculations and the CITATION module for reactor core level calculations. The results show that (Th-233U)O2 offers the most stable Keff over a 12-year operating period, consistently remaining above the criticality threshold at all fuel volume fractions. In addition, this fuel type exhibits the most uniform power density distribution and the lowest PPF values, reducing the potential for thermal hotspots. (Th-233U)O2 fuel can achieve a burnup level of around 50,000 MW/ton, which aligns with SMR-BWR standards. UO2 and (Th-235U)O2 fuels show a more pronounced Keff decrease and less favorable power distribution characteristics. These findings underline the potential of (Th-233U)O2 as a promising candidate for long-cycle, continuous SMR-BWR applications without refueling

Author Biographies

Boni Lapanporo, Universitas Tanjungpura

Assistant Professor

Department of Physics, Faculty of Mathematics and Natural Sciences

Zaki Su’ud, Institut Teknologi Bandung; Institut Teknologi Bandung

Professor

Department of Physics, Faculty of Mathematics and Natural Sciences

Nuclear Physics & Biophysics Research Division

References

  1. Lapanporo, B. P., Su’ud, Z. (2022). Parametric Study of Thorium Fuel Utilization on Small Modular Pressurized Water Reactors (PWR). Journal of Physics: Conference Series, 2243 (1), 012062. https://doi.org/10.1088/1742-6596/2243/1/012062
  2. Science, N. (2013). Minor Actinide Burning in Thermal Reactors A Report. Working Party. Nuclear Energy Agency.
  3. Humphrey, U. E., Khandaker, M. U. (2018). Viability of thorium-based nuclear fuel cycle for the next generation nuclear reactor: Issues and prospects. Renewable and Sustainable Energy Reviews, 97, 259–275. https://doi.org/10.1016/j.rser.2018.08.019
  4. Du Toit, M. H., Van Niekerk, F., Amirkhosravi, S. (2024). Review of thorium-containing fuels in LWRs. Progress in Nuclear Energy, 170, 105136. https://doi.org/10.1016/j.pnucene.2024.105136
  5. Galahom, A. A., Mohsen, M. Y. M., Amrani, N. (2022). Explore the possible advantages of using thorium-based fuel in a pressurized water reactor (PWR) Part 1: Neutronic analysis. Nuclear Engineering and Technology, 54 (1), 1–10. https://doi.org/10.1016/j.net.2021.07.019
  6. Lobo, M. C. A., Stefani, G. L. de. (2024). Thorium as nuclear fuel in Brazil: 1951 to 2023. Nuclear Engineering and Design, 419, 112912. https://doi.org/10.1016/j.nucengdes.2024.112912
  7. Gorton, J. P., Collins, B. S., Nelson, A. T., Brown, N. R. (2019). Reactor performance and safety characteristics of ThN-UN fuel concepts in a PWR. Nuclear Engineering and Design, 355, 110317. https://doi.org/10.1016/j.nucengdes.2019.110317
  8. Shaposhnik, Y., Shwageraus, E., Elias, E. (2013). Core design options for high conversion BWRs operating in Th–233U fuel cycle. Nuclear Engineering and Design, 263, 193–205. https://doi.org/10.1016/j.nucengdes.2013.04.018
  9. Abdelghafar Galahom, A., Bashter, I. I., Aziz, M. (2015). Design of an MCNPX model to simulate the performance of BWRs using thorium as fuel and its validation with HELIOS code. Annals of Nuclear Energy, 77, 393–401. https://doi.org/10.1016/j.anucene.2014.11.030
  10. Insulander Björk, K., Fhager, V., Demazière, C. (2011). Comparison of thorium-based fuels with different fissile components in existing boiling water reactors. Progress in Nuclear Energy, 53 (6), 618–625. https://doi.org/10.1016/j.pnucene.2010.03.004
  11. Carvalho, K. de A., Barros, G., Araujo, M. H. S., Vieira, T. A. S., Gonçalves, R. C., Silva, V., Santos, A. A. C. dos. (2025). Neutronic analysis and safety considerations in an innovative nuscale-like core merging thorium dioxide and reprocessed fuel. Nuclear Engineering and Design, 433, 113874. https://doi.org/10.1016/j.nucengdes.2025.113874
  12. Lapanporo, B. P., Su’ud, Z., Mustari, A. P. A. (2024). Comparison of the neutronic properties of the (Th-233U)O2, (Th-233U)C, and (Th-233U)N fuels in small long-life PWR cores with 300, 400, and 500 MWth of power. Nukleonika, 69(1), 3–12. https://doi.org/10.2478/nuka-2024-0001
  13. BWRX-300 General Description (2023). GE Hitachi Nuclear Energy. Available at: https://www.gevernova.com/content/dam/gepower-new/global/en_US/images/gas-new-site/en/bwrx-300/005N9751_Rev_BWRX-300_General_Description.pdf
  14. Lapanporo, B. P., Su’ud, Z., Mustari, A. P. A. (2024). Neutronic design of small modular long­life pressurized water reactor using thorium carbide fuel at a power level of 300–500 MWth. Eastern-European Journal of Enterprise Technologies, 1 (8 (127)), 18–27. https://doi.org/10.15587/1729-4061.2024.290996
  15. Insulander Björk, K. (2013). A BWR fuel assembly design for efficient use of plutonium in thorium–plutonium fuel. Progress in Nuclear Energy, 65, 56–63. https://doi.org/10.1016/j.pnucene.2013.01.010
Evaluation of thorium-based fuels for 12-year operation of small modular BWR without refueling

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Published

2025-08-28

How to Cite

Lapanporo, B., & Su’ud, Z. (2025). Evaluation of thorium-based fuels for 12-year operation of small modular BWR without refueling. Eastern-European Journal of Enterprise Technologies, 4(5 (136), 6–14. https://doi.org/10.15587/1729-4061.2025.335730

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Section

Applied physics