Numerical modelling of modular high-temperature gas-cooled reactors with thorium fuel

• Autorzy: Oettingen Mikołaj , Cetnar Jerzy

Identyfikatory

DOI

10.2478/nuka-2021-0020

• Konferencja: International Conference on Development and Applications of Nuclear Technologies NUTECH-2020 (04–07.10.2020; Warsaw, Poland)
• Języki publikacji: EN

Abstrakty

EN

The volumetric homogenization method for the simplified modelling of modular high-temperature gas-cooled reactor core with thorium-uranium fuel is presented in the paper. The method significantly reduces the complexity of the 3D numerical model. Hence, the computation time associated with the time-consuming Monte Carlo modelling of neutron transport is considerably reduced. Example results comprise the time evolutions of the effective neutron multiplication factor and fissionable isotopes (233U, 235U, 239Pu, 241Pu) for a few configurations of the initial reactor core.

Słowa kluczowe

EN

HTR; homogenization; thorium; Monte Carlo

• Wydawca: Institute of Nuclear Chemistry and Technology
• Czasopismo: Nukleonika
• Rocznik: 2021
• Tom: Vol. 66, No. 4
• Strony: 133--138
• Opis fizyczny: Bibliogr. 9 poz., rys.

Twórcy

autor

Oettingen Mikołaj

• AGH University of Science and Technology Faculty of Energy and Fuels Mickiewicza 30 Ave., 30-059 Krakow, Poland

• https://orcid.org/0000-0001-7499-7585

autor

Cetnar Jerzy

• National Centre for Nuclear Research Andrzeja Sołtana 7 Str., 05-400 Otwock-Świerk, Poland

• https://orcid.org/0000-0002-0163-3331

Bibliografia

• 1. Talamo, A., Ji, W., Cetnar, J., & Gudowski, W. (2006). Comparison of MCB and MONTEBURNS Monte Carlo burnup codes on a one-pass deep burn. Ann. Nucl.Energy, 33(14/15), 1176–1188. doi.org/10.1016/j.anucene.2006.08.006.
• 2. International Atomic Energy Agency. (2012). Role of thorium to supplement fuel cycles of future nuclear energy systems. Vienna: IAEA. (Nuclear Energy Series NF-T-2.4).
• 3. International Atomic Energy Agency. (2005). Thorium fuel cycle – Potential benefi ts and challenges. Vienna: IAEA. (IAEA-TECDOC-1450).
• 4. Shamanin, I. V., Grachev, V. M., Chertkov, Yu. B., Bedenko, S. V., Mendoza, O., & Knyshev, V. V. (2018).Neutronic properties of high-temperature gas-cooled reactors with thorium fuel. Ann. Nucl. Energy, 113, 286–293. DOI: 10.1016/j.anucene.2017.11.045.
• 5. Oettingen, M., & Stanisz, P. (2018). Monte Carlo modelling of Th-Pb fuel assembly with californium neutron source. Nukleonika, 63(3), 87–91. DOI: 10.2478/nuka-2018-0011.
• 6. Cetnar, J. (2006). Solution of Bateman equations for nuclear transmutations. Ann. Nucl. Energy, 33, 640–645. DOI: 10.1016/j.anucene.2006.02.004.
• 7. Oettingen, M., Cetnar, J., & Mirowski, T. (2015). The MCB code for numerical modelling of fourth generation nuclear reactors. Computer Science, 16, 329–350. DOI: 10.7494/csci.2015.16.4.329.
• 8. Cetnar, J., Stanisz, P., & Oettingen, M. (2021). Linear chain method for numerical modelling of burnup systems. Energies, 14, 1520. https://doi.org/10.3390/en14061520.
• 9. Oettingen, M. (2021). Assessment of the radiotoxicity of spent nuclear fuel from a fleet of PWR reactors (2021). Energies, 14, 3094. https://doi.org/10.3390/en14113094.

Uwagi

Opracowanie rekordu ze środków MNiSW, umowa Nr 461252 w ramach programu "Społeczna odpowiedzialność nauki" - moduł: Popularyzacja nauki i promocja sportu (2021).