Multilateral evaluation of the effects of utilizing thorium oxide in the Bushehr VVER-1000 reactor
-
Mohammadreza Lotfalian
and
Masoud Mansouri
Abstract
The use of thorium oxide in thermal reactors is currently being explored due to its promising outcomes. One primary concern is how to reduce the pollution of core components and nuclear waste. The inclusion of 232Th in the reactor leads to the production of 233U and decreases the formation of minor actinides. On the other hand, 238U increases the production of 239Pu, a toxic and strategically significant isotope, along with minor actinides. Therefore, the potential of thorium to reduce the production of 239Pu, one of the most harmful isotopes, can be assessed in the Bushehr VVER-1000 reactor. This study involved replacing some uranium in the Bushehr VVER-1000 reactor with 232Th. The research focused on examining the environmental impact of nuclear waste, including activity, chain reactions, and isotope levels, over a two-year period. The impact of the new fuel substitution was evaluated in the Bushehr reactor, which has a power of 3,000 MWth, in three scenarios: thorium addition to 1.6 % enriched assemblies, thorium addition to 2.4 % enriched assemblies, and thorium addition to 3.6 % enriched assemblies. These changes were analyzed in terms of nuclear waste contamination, plutonium production, fuel burn-up, and conversion ratio, and compared to the reactor using UO2 fuel. The simulation was conducted using the MCNPX 2.6.0 computational code and heterogeneous geometry. The results indicate that nuclear waste pollution decreased when thorium was added to the 1.6 % and 2.4 % enriched assemblies, but increased when added to the 3.6 % assemblies. Additionally, fuel burn-up increased with the addition of thorium in the 1.6 % and 2.4 % assemblies, but decreased in the 3.6 % assemblies. However, the conversion ratio increased in all cases. The fuel temperature coefficient (FTC), moderator temperature coefficient (MTC), and void coefficient (VC) were calculated and evaluated.
-
Research ethics: Not applicable.
-
Author contributions: The authors have accepted responsibility for the entire content of this manuscript and approved its submission.
-
Competing interests: The authors state no conflict of interest.
-
Research funding: None declared.
-
Data availability: Not applicable.
References
Abdelghafar Galahom, A., Salah Khaliil, A., Alnassar, N., Reda, and Sonia, M. (2024). Discussing the possibility of using thorium-based fuels as an alternative fuel to uranium dioxide fuel for APR-1400 reactor. Nucl. Eng. Des. 417: 112817, https://doi.org/10.1016/j.nucengdes.2023.112817.Search in Google Scholar
Abdelghafar Galahom, A. and Ibrahim, A. (2022). Integrated analysis to investigate the viability of using Thorium-based fuel instead of traditional fuel in CANDU reactor. Nucl. Eng. Des. 398: 111969, https://doi.org/10.1016/j.nucengdes.2022.111969.Search in Google Scholar
Abdelghafar Galahom, A. (2021). Examine the possibility of increasing the plutonium incineration rate in the current operating pressurized water reactor. Prog. Nucl. Energy 142: 104026, https://doi.org/10.1016/j.pnucene.2021.104026.Search in Google Scholar
Abdelghafar Galahom, A., Elazaka, A.I., and Tikhomirov, G.V. (2021). Searching for managing the reactivity and increasing the fuel cycle life in the PWR by an untraditional method. Nucl. Eng. Des. 383: 111433, https://doi.org/10.1016/j.nucengdes.2021.111433.Search in Google Scholar
Abdelghafar Galahom, A. and Mohamad Sharaf, I. (2021). Finding a suitable fuel type for the disposal of the accumulated minor actinides in the spent nuclear fuel in PWR. Prog. Nucl. Energy 136: 103749, https://doi.org/10.1016/j.pnucene.2021.103749.Search in Google Scholar
Abdelghafar Galahom, A. (2020). Investigate the possibility of burning weapon-grade plutonium using a concentric rods BS assembly of VVER-1200. Ann. Nucl. Energy 148: 107758, https://doi.org/10.1016/j.anucene.2020.107758.Search in Google Scholar
Afzali, M., Athari Allaf, M., Jahanfarnia, G., and Kheradmand Saadi, M. (2022). Optimization and burn up calculations of BNPP’s reactor core with the new generation fuels (TVS-2M) by artificial neural network. Prog. Nucl. Energy 150: 104290, https://doi.org/10.1016/j.pnucene.2022.104290.Search in Google Scholar
Alwaeli, M. and Mannheim, V. (2022). Investigation into the current state of nuclear energy and nuclear waste management - a state-of-the-art review. Energies 15: 4275, https://doi.org/10.3390/en15124275.Search in Google Scholar
Bushehr NPP Final Safety Analysis Report (2007). Sheet 4-32. At. Energy Org. Iran Chapter 4(Sheet 4-32).Search in Google Scholar
Chroneos, A., Goulatis, I., Daskalopulu, A., and Tsoukalas, L.H. (2023). Thorium fuel revisited. Prog. Nucl. Energy 164: 104839, https://doi.org/10.1016/j.pnucene.2023.104839.Search in Google Scholar
Elazaka, A.I., Tikhomirov, G.V., Savander, V.I., Abdel-Rahman, Mohamed A.E., and Abdelghafar Galahom, A. (2021). Investigation of a new approach for regulating the reactivity and achieving economic feasibility using thorium in a blanket-seed assembly of pressurized water reactors. Int. J. Energy Res. 46: 6112–6125, https://doi.org/10.1002/er.7551.Search in Google Scholar
Ganda, F., Arias, F.J., Vujic, J., and Greenspan, E. (2012). Self-sustaining thorium boiling water reactors. Sustainability 4: 2472–2497, https://doi.org/10.3390/su4102472.Search in Google Scholar
Györgi, H. and Czifrus, Sz. (2016). The utilization of thorium in Generation IV reactors. Prog. Nucl. Energy 93: 306–317, https://doi.org/10.1016/j.pnucene.2016.09.007.Search in Google Scholar
Hirschhorn, J., Greenquist, I., Wysocki, A., and Capps, N. (2023). Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility part 2: high-burn up steady-state operating and fuel performance conditions. Ann. Nucl. Energy 192: 109952, https://doi.org/10.1016/j.anucene.2023.109952.Search in Google Scholar
Korkmaz, M.E., Agar, O., and Büyüker, E. (2014). Burnup analysis of the VVER-1000 reactor using thorium-based fuel. Kerntechnik 79: 478–483, https://doi.org/10.3139/124.110449.Search in Google Scholar
Miguirditchian, M., Grandjean, S., Sorel, C., Vanel, V., Delahaye, T., Pillon, S., Ramond, L., Ladirat, C., Giboire, I., Poinssot, C., et al. (2017). Advanced concepts for uranium and plutonium multi-recycling. In: GLOBAL international nuclear fuel cycle conference. HAL Open Science, Seoul, South Korea. https://hal.science/hal-02418116.Search in Google Scholar
Mohsen, M.Y.M., Abdel-Rahman, M.A.E., Omar, A., Nassar Alnassar, A., and Abdelghafar Galahom, A. (2024). Searching for the viability of using thorium-based accidenttolerant fuel for VVER-1200. Nucl. Eng. Technol. 56: 167–179, https://doi.org/10.1016/j.net.2023.09.021.Search in Google Scholar
Selvam, C.D., Yuvarajan, D., and Raja, T. (2024). Study on analysing the potential benefits of utilizing nuclear waste for biodiesel production. Kerntechnik 89: 368–381, https://doi.org/10.1515/kern-2024-0010.Search in Google Scholar
Slovic, P., Flynn, J.H., and Layman, M. (1991). Perceived risk, trust, and the politics of nuclear waste. Science 254(5038): 1603–1607, https://doi.org/10.1126/science.254.5038.1603.Search in Google Scholar PubMed
Smith, J., Marks, N., and Irwin, T. (2023). The risks of radioactive wastewater release. Science 382(6666): 31–33, https://doi.org/10.1126/science.adi5446.Search in Google Scholar PubMed
Tochaikul, G., Phattanasub, A., Khemkham, P., Saengthamthawee, K., Danthanavat, N., and Moonkum, N. (2022). Radioactive waste treatment technology: a review. Kerntechnik 87: 208–225, https://doi.org/10.1515/kern-2021-1029.Search in Google Scholar
Trellue, H.R., Bathke, C.G., and Sadasivan, P. (2011). Neurotics and material attractiveness for PWR thorium systems using Monte carol techniques. Prog. Nucl. Energy 53: 698–707, https://doi.org/10.1016/j.pnucene.2011.04.007.Search in Google Scholar
Tucker, L.P. and Usman, S. (2018). Thorium-based mixed oxide fuel in a pressurized water reactor: a burnup analysis with MCNP. Ann. Nucl. Energy 111: 163–175, https://doi.org/10.1016/j.anucene.2017.08.057.Search in Google Scholar
Uguru, E.H., Abdul Sani, S.F., Khandaker, M.U., Rabir, M.H., Karim, J.A., Onah, D.U., and Bradley, D.A. (2020). Burn-up calculation of the neutronic and safety parameters of thorium-uranium mixed oxide fuel cycle in a Westinghouse small modular reactor. Int. J. Energy Res. 45: 12013–12028, https://doi.org/10.1002/er.6000.Search in Google Scholar
© 2024 Walter de Gruyter GmbH, Berlin/Boston
Articles in the same Issue
- Frontmatter
- Multilateral evaluation of the effects of utilizing thorium oxide in the Bushehr VVER-1000 reactor
- Comparison of modeling methods for the effective diffusivities of IO3− estimated in compacted bentonite using through-diffusion tests under aerobic conditions
- Analysis of initial core and time dependent fuel burnup for high temperature testing reactors (HTTRs)
- A detection and defense security system design for nuclear waste storage against stealth terrorists attack
- Optimization of ECR assisted pre-ionization in GLAST-III via Multiphysics simulation
- Fuzzy reliability algorithm for the shutdown system of research reactor
- System theory safety analysis of network malfunction in nuclear power plant distributed control systems
- Two phase flow analysis of micro channel evaporator to investigate effect of geometry on pressure and heat transfer coefficient with respect to volume of fraction
- Methodology for analyzing dose consequence using atmospheric dispersion code A2CDOSE
- Reliability analysis of digital reactor protection systems in floating nuclear power plants
- Study on comprehensive evaluation method of mental workload level
- Integrating reliability analysis into MBSE for FPGA-based safety critical I&C system design in nuclear power plants
- Calendar of events
Articles in the same Issue
- Frontmatter
- Multilateral evaluation of the effects of utilizing thorium oxide in the Bushehr VVER-1000 reactor
- Comparison of modeling methods for the effective diffusivities of IO3− estimated in compacted bentonite using through-diffusion tests under aerobic conditions
- Analysis of initial core and time dependent fuel burnup for high temperature testing reactors (HTTRs)
- A detection and defense security system design for nuclear waste storage against stealth terrorists attack
- Optimization of ECR assisted pre-ionization in GLAST-III via Multiphysics simulation
- Fuzzy reliability algorithm for the shutdown system of research reactor
- System theory safety analysis of network malfunction in nuclear power plant distributed control systems
- Two phase flow analysis of micro channel evaporator to investigate effect of geometry on pressure and heat transfer coefficient with respect to volume of fraction
- Methodology for analyzing dose consequence using atmospheric dispersion code A2CDOSE
- Reliability analysis of digital reactor protection systems in floating nuclear power plants
- Study on comprehensive evaluation method of mental workload level
- Integrating reliability analysis into MBSE for FPGA-based safety critical I&C system design in nuclear power plants
- Calendar of events
