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Application of genetic algorithms in optimization of SFR nuclear reactor design

Treść / Zawartość
Identyfikatory
Warianty tytułu
Konferencja
International Conference on Development and Applications of Nuclear Technologies NUTECH-2020 (04–07.10.2020; Warsaw, Poland)
Języki publikacji
EN
Abstrakty
EN
This work presents a demonstrational application of genetic algorithms (GAs) to solve sample optimization problems in the generation IV nuclear reactor core design. The new software was developed implementing novel GAs, and it was applied to show their capabilities by presenting an example solution of two selected problems to check whether GAs can be used successfully in reactor engineering as an optimization tool. The 3600 MWth oxide core, which was based on the OECD/NEA sodium-cooled fast reactor (SFR) benchmark, was used a reference design [1]. The first problem was the optimization of the fuel isotopic inventory in terms of minimizing the volume share of long-lived actinides, while maximizing the effective neutron multiplication factor. The second task was the optimization of the boron shield distribution around the reactor core to minimize the sodium void reactivity effect (SVRE). Neutron transport and fuel depletion simulations were performed using Monte Carlo neutron transport code SERPENT2. The simulation resulted in an optimized fuel mixture composition for the selected parameters, which demonstrates the functionality of the algorithm. The results show the efficiency and universality of GAs in multidimensional optimization problems in nuclear engineering.
Czasopismo
Rocznik
Strony
139--145
Opis fizyczny
Bibligr. 24 poz., rys.
Twórcy
  • Warsaw University of Technology Faculty of Physics Koszykowa 75 Str., 00-665, Warsaw, Poland
  • Warsaw University of Technology Faculty of Physics Koszykowa 75 Str., 00-665, Warsaw, Poland
  • National Centre for Nuclear Research Andrzeja Sołtana 7 Str., 05-400 Otwock-Świerk, Poland
  • Warsaw University of Technology Institute of Heat Engineering Nowowiejska 21/25 Str., 00-665, Warsaw, Poland
Bibliografia
  • 1. NEA/OECD. (2016). Benchmark for neutronic analysis of sodium-cooled fast reactor cores with various fuel types and core sizes. OECD Nuclear Energy Agency. Available from https://www.oecdnea.org/upload/docs/application/pdf/2020-01/nscr2015-9.pdf.
  • 2. OECD/NEA. (2014). Technology roadmap update for Generation IV nuclear energy systems. OECD Nuclear Energy Agency. Available from https://www.gen-4.org/gif/upload/docs/application/pdf/2014-03/gif-tru2014.pdf.
  • 3. Waltar, A. E., Todd, D. R., & Tsvetkov, P. V. (Eds.).(2013). Fast spectrum reactors. Springer.
  • 4. Ogawa, M. (2016). Proposals of new basic concepts on safety and radioactive waste and of new High Temperature Gas-cooled Reactor based on these basic concepts. Nucl. Eng. Des., 308, 133–141. https://doi.org/10.1016/j.nucengdes.2016.08.028.
  • 5. El-Emam, R. S., Dincer, I., & Zamfi rescu, C. (2019).Enhanced CANDU reactor with heat upgrade for combined power and hydrogen production. Int. J. Hydrog.Energy, 44, 23580–23588. https://doi.org/10.1016/j.ijhydene.2019.06.181.
  • 6. Yoo, J., Chang, J., Lim, J. -Y., Cheon, J. -S., Lee, T.-H., Kim, S. K., Lee, K. L., & Joo, H. -K. (2016).Overall system description and safety characteristics of Prototype Gen IV sodium cooled fast reactor in Korea. Nucl. Eng. Technol., 48, 1059–1070. https://doi.org/10.1016/j.net.2016.08.004.
  • 7. Rachkov, V., & Ashurko, Y. (2010). Review of SFR safety related operational experience. In First Joint IAEA–GIF Workshop on Operational and Safety Aspects of Sodium Cooled Fast Reactors, 23–25 May 2010, Vienna, Austria. Available from IAEA INIS database, https://inis.iaea.org/collection/NCLCollectionStore/_Public/49/104/49104075.pdf?r=1.
  • 8. Aoto, K., Dufour, P., Hongyi, Y., Glatz, J. P., Kim, Y., Ashurko, Y., Hill, R., & Uto, N. (2014). A summary of sodium-cooled fast reactor development. Prog. Nucl. Energy, 77, 247–265. https://doi.org/http://dx.doi.org/10.1016/j.pnucene.2014.05.008.
  • 9. Chetal, S. C., & Chellapandi, P. (2013). Indian fast reactor technology: Current status and future programme. Sadhana, 38(5), 795–815. https://doi.org/10.1007/s12046-013-0167-8.
  • 10. Puthiyavinayagam, P., Selvaraj, P., Balasubramaniyan, V., Raghupathy, S., Velusamy, K., Devan, K., Nashine, B. K., Padma Kumar, G., Suresh kumar, K. V., Varatharajan, S., Mohanakrishnan, P., Srinivasan, G., & Bhaduri, A. K. (2017). Development of fast breeder reactor technology in India. Prog. Nucl. Energy, 101, 19–42. https://doi.org/10.1016/j.pnucene.2017.03.015.
  • 11. Holland, J. H. (1992). Adaptation in natural and artificial systems: an introductory analysis with applications to biology, control, and artificial intelligence. MIT Press.
  • 12. Goldberg, D. E. (1979). Genetic algorithms in search, optimization, and machine learning. Addison-Wesley Publishing Company, Inc. https://www.gbv.de/dms/ilmenau/toc/01600020X.PDF.
  • 13. Israeli, E., & Gilad, E. (2017). Novel genetic algorithms for loading pattern optimization using state-of-the-art operators and a simple test case.J. Nucl. Eng. Radiat. Sci., 3, 1–10. https://doi.org/10.1115/1.4035883.
  • 14. Hill, T. (2014). Pressurised water reactor in-core fuel management by tabu search. Ann. Nucl. Energy, 75, 64–71. https://www.repository.cam.ac.uk/bitstream/handle/1810/245632/Tasha-Hill-revised-paper.pdf?sequence=1.
  • 15. Pereira, C. M. N. A., Schirru, R., & Martinez, A. S. (2000). Genetic algorithms applied to nuclear reactor design optimization. In Da Ruan (Ed.), Fuzzy systems and soft computing in nuclear engineering (pp. 315–334). Springer. https://doi.org/10.1007/978-3-7908-1866-6_14.
  • 16. Martín Del Campo, C., François, J. L., & López, H. . (2001). AXIAL: A system for boiling water reactor fuel assembly axial optimization using genetic algorithms. Ann. Nucl. Energy, 28(16), 1667–1682.https://doi.org/10.1016/S0306-4549(01)00002-0.
  • 17. Martín-del-Campo, C., Palomera-Pérez, M. Á., & François, J. L. (2009). Advanced and flexible genetic algorithms for BWR fuel loading pattern optimization. Ann. Nucl. Energy, 36(10), 1553–1559. https://doi.org/10.1016/j.anucene.2009.07.013.
  • 18. Ortiz, J. J., & Requena, I. (2004). An order coding genetic algorithm to optimize fuel reloads in a nuclear boiling water reactor. Nucl. Sci. Eng., 146(1), 88–98.https://doi.org/10.13182/NSE04-A2395.
  • 19. Leppänen, J. (2015, June 18). Serpent – a continuousenergy Monte Carlo reactor physics burnup calculation code – User’s manual. Available from http://montecarlo.vtt.fi /download/Serpent_manual.pdf.
  • 20. Leppänen, J. (2007). Development of a new Monte Carlo reactor physics code. PhD Thesis, Helsinki University of Technology.
  • 21. Leppänen, J., Pusa, M., Viitanen, T., Valtavirta, V., & Kaltiaisenaho, T. (2015). The Serpent Monte Carlo code: Status, development and applications in 2013. Ann. Nucl. Energy, 82, 142–150. https://doi.org/10.1016/j.anucene.2014.08.024.
  • 22. Beck, T., Blanc, V., Chapoutier, N., Escleine, J., Gauthier, L., Haubensack, D., Occhipinti, D., Pelletier, M., Phelip, M., Perrin, B., & Venard, C. (2020). Conceptual design of fuel and radial shielding sub-assemblies for ASTRID. HAL Id: cea-02435081. Available from https://hal.archives-ouvertes.frcea-02435081.
  • 23. Venard, C., Coquelet, C., Conti, A., Gentet, D., Lamagnere, P., Lavastre, R., Gauthe, P., Bernardin, B., Beck, T., Lorenzo, D., Scholer, Ac., & Vernier, D. (2019). The astrid core at the end of the conceptual design phase. HAL Id: hal-02419651.
  • 24. Guo, H., & Buiron, L. (2018). Innovative sodium fast reactors control rod design. HAL Id: hal-01907183.Available from https://hal.archives-ouvertes.fr/hal01907183.
Uwagi
Opracowanie rekordu ze środków MNiSW, umowa Nr 461252 w ramach programu "Społeczna odpowiedzialność nauki" - moduł: Popularyzacja nauki i promocja sportu (2021).
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-916c1fbf-b395-45bb-83d8-6824967aee23
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