Home Ensuring safety of new, advanced small modular reactors for fundamental safety and with an optimal main heat transport systems configuration
Article
Licensed
Unlicensed Requires Authentication

Ensuring safety of new, advanced small modular reactors for fundamental safety and with an optimal main heat transport systems configuration

  • Avinash J. Gaikwad EMAIL logo , Naresh K. Maheshwari , Dinesh K. Chandrakar , R. B. Solanki , Bhanuprakash and Uttam K. Paul
Published/Copyright: May 12, 2023
Become an author with De Gruyter Brill

Abstract

Many countries are considering Small and Modular Reactors as a viable alternative to counter the climate-change/global-warming with a quick deployment of green, carbon free nuclear energy option in the energy mix. Proponents of SMRs claim that these designs rely more on enhanced inherent/engineered safety and passive features with novel concepts. SMRs are being designed to be fabricated at a factory and then transported as ‘modules’ to the sites for installation either as a single module or multiple module plant. There are many variant of SMRs under considerations/design/construction/commissioning/operation states and majority of the, more than 70 odd SMRs are in the design stage. The paper focuses on safety aspects while addressing the fundamental safety requirement that are derived from fundamental safety principles, the acceptance criteria, the expected/envisaged safety targets and not only the economic impact/considerations. The assessment basis for requirements towards safety enhancements and their extent of assurance in the design are highlighted against the claims made. Ensuring SMR safety with respect to the fundamental safety functions will depend on the foreseen/predicted fission product releases, following overheating of the fuel, during the worst/credible accident conditions and likelihood of occurrence of these accidents. Innovations in the development of advanced fuel, deploying passive safety systems, novel concepts in main heat transport system configuration and advanced features in instrumentation can help in realising the goal of ensured enhanced safety in the SMRs, both in preventive and mitigation domains during severe accidents. Enhancements in the acceptance criteria and deterministic and probabilistic safety targets is also expected and may be envisaged. The paper brings out the challenges faced in the design and regulation of the new NPPs, while addressing fundamental safety principles implementation, generic, specific safety issues, and only genuine innovations can ensure and improve the safety. Aspects related to passive systems and the optimal main heat removal system configuration of the NPPs are also discussed. The aspects related to concurrent design and regulation of new NPPs including SMRs also has been brought out in the paper.


Corresponding author: Avinash J. Gaikwad, Homi Bhabha Institute of Technology (HBNI), Anushaktinagar, Mumbai 400094, India; and Atomic Energy Regulatory Board (AERB), Anushaktinagar, Mumbai 400094, India, E-mail:

  1. Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.

  2. Research funding: None declared.

  3. Conflict of interest statement: The authors declare no conflicts of interest regarding this article.

References

Akbari, R., Ochbelagh, D.R., Gharib, A., Maiorino, J.R., and D’Auria, F. (2020). Small modular reactor full scope core optimization using Cuckoo Optimization Algorithm. Prog. Nucl. Energy 122: 103271, https://doi.org/10.1016/j.pnucene.2020.103271.Search in Google Scholar

Arul, A.J., Iyer, N.K., and Velusamy, K. (2009). Adjoint operator approach to functional reliability analysis of passive fluid dynamical systems. Reliab. Eng. Syst. Saf. 94: 1917–1926, https://doi.org/10.1016/j.ress.2009.06.008.Search in Google Scholar

Blandford, E., Brumback, K., Fick, L., Gerardi, C., Haugh, B., Hillstrom, E., Johnson, K., Peterson, P.F., Rubio, F., Sarikurt, F.S., et al.. (2020). Kairos power thermal hydraulics research and development. Nucl. Eng. Des. 364: 110636, https://doi.org/10.1016/j.nucengdes.2020.110636.Search in Google Scholar

Blue, L.S. (1996). The gas turbine-modular helium reactor for the next fifty years of nuclear power. In: Kursunoglu, B.N., Mintz, S.L., and Perlmutter, A. (Eds.), Economics and Politics of energy. Springer, Boston, MA.Search in Google Scholar

Boado Magan, H., Delmastro, D.F., Markiewicz, M., Lopasso, E., Diez, F., Giménez, M., Rauschert, A., Halpert, S., Chocrón, M., Dezzutti, J.C., et al.. (2011). CAREM prototype construction and licensing status, proceedings of an international conference on opportunities and challenges for water cooled reactors in the 21st century. IAEA-CN-164-5S01, Available at: <http://www-pub.iaea.org/MTCD/Publications/PDF/P1500_CD_Web/htm/pdf/topic5/5S01_D.%20Delmastro.pdf> (Accessed 10 March 2023).Search in Google Scholar

Bortot, S., Moisseytsev, A., Sienicki, J.H., and Artioli, C. (2011). Core design investigation for a SUPERSTAR small modular lead-cooled fast reactor demonstrator. Nucl. Eng. Des. 241: 3021–3031, https://doi.org/10.1016/j.nucengdes.2011.04.012.Search in Google Scholar

CANDU Energy Inc (2023). CANDU SMR: original Canadian solution, Available at: <https://www.snclavalin.com/∼/media/Files/S/SNC-Lavalin/download-centre/en/brochure/our-candu-smr_en.pdf> (Accessed 10 March 2023).Search in Google Scholar

Carelli, M.D., Petrović, B., Čavlina, N., and Grgić, D. (2005). IRIS (international reactor innovative and secure) design overview and deployment prospects. In: Proceedings of international conference nuclear energy for New Europe 2005, Bled, Slovenia September 5–8 2005.Search in Google Scholar

Cinotti, L. and Grasso, G. (2021). LFR-SMR: affordable solutions for multiple needs. Proceedings of the technical meeting Benefits and Challenges of small modular fast reactors. IAEA-TECDOC-1972, Available at: <https://www-pub.iaea.org/MTCD/Publications/PDF/TE-1972web.pdf> (Accessed 10 March 2023).Search in Google Scholar

D’Auria, F. and Galassi, G.M. (2000). Methodology for the evaluation of the reliability of passive systems. University of Pisa, DIMNP, NT 420 (00), Pisa, Italy.Search in Google Scholar

Dmitriev, S.M., Kurachenkov, A.V., and Petrunin, V.V. (2020). Scientific-technical and economic aspects for development of innovative reactor plants for small and medium nuclear power plants. J. Phys. Conf. 1683: 042032, https://doi.org/10.1088/1742-6596/1683/4/042032.Search in Google Scholar

Furukawa, K., Greaves, E., Erbay, L., Hron, M., and Kato, Y. (2011). New sustainable secure nuclear industry based on thorium molten-salt nuclear energy synergetics (THORIMS-NES). Chapter 17. In: Tsvetkov, P.V. (Ed.), Nuclear power – deployment, Operation and sustainability.10.5772/19198Search in Google Scholar

Gaikwad, A.J., Vijayan, P.K., Bhartya, S., Iyer, K., Kumar, R., Contractor, A.D., Lele, H.G., Vhora, S.F., Maurya, A.K., Ghosh, A.K., et al.. (2008). Effect of coolant inventories and parallel loop interconnections on the natural circulation in various heat transport systems of a nuclear power plant during station blackout. Sci. Technol. Nucl. Install. 2008: 458316, https://doi.org/10.1155/2008/458316.Search in Google Scholar

Gaikwad, A.J., Maheshwari, N.K., Obaidurrahman, K., Gupta, A., and Pradhan, S.K. (2020). Optimal Main Heat Transport system configuration for a nuclear power plant. Nucl. Eng. Des. 359: 110474, https://doi.org/10.1016/j.nucengdes.2019.110474.Search in Google Scholar

GE Hitachi Nuclear Energy (2023). The BWRX-300 small Modular reactor, Available at: <https://nuclear.gepower.com/build-a-plant/products/nuclear-power-plants-overview/bwrx-300> (Accessed 10 March 2023).Search in Google Scholar

Hargraves, R. and Moir, R. (2010). Liquid Fluoride Thorium Reactors: an old idea in nuclear power gets re-examined. Am. Sci. 98: 304–313, https://doi.org/10.1511/2010.85.304.Search in Google Scholar

Hidayati, A.N., Waris, A., Irwanto, D., and Pramutadi, A. (2019). HTTR 30MWth Reactor with homogeneous (Th,U)O2-Fuel. J. Phys. Conf. 120: 012134, https://doi.org/10.1088/1742-6596/1204/1/012134.Search in Google Scholar

Hwang, I.S. (2021). MicroURANUS: a microreactor for maritime decarbonization with zero greenhouse gases. IGlobeNews 17. November 2021, Available at: <https://www.iglobenews.org/microuranus-a-microreactor-for-maritime-decarbonization-with-zero-greenhouse-gases/> (Accessed 10 March 2023).Search in Google Scholar

IAEA (2011). Status report 66 – VER-300, Available at: <https://aris.iaea.org/PDF/VBER-300.pdf> (Accessed 10 March 2023).Search in Google Scholar

IAEA (2006). Fundamental safety principles, IAEA Safety Standard Series IAEA-SF-1.Search in Google Scholar

IAEA (2020). Advances in small modular reactor technology developments, A Supplement to: IAEA Advanced Reactors Information System (ARIS) 2020 Edition, Available at: <https://aris.iaea.org/Publications/SMR_Book_2020.pdf> (Accessed 10 March 2023).Search in Google Scholar

Li, X., Li, L., Peng, L., Chen, X., Meng, Z., and Chen, Y. (2018). Conceptual core design of HAPPY200 reactor. In: Proceedings of 26th international conference on nuclear engineering, ICONE26, July 22–26, 2018, London, England, ICONE26:82125.Search in Google Scholar

Liao, J., Ferroni, P., Wright, R.F., Bachrach, U., Scobel, J.H., Sofu, T., Tentner, A.M., Lee, S.J., Epstein, M., Frignani, M., et al.. (2021). Development of phenomena identification and ranking table for Westinghouse lead fast reactor’s safety. Prog. Nucl. Energy 131: 103577, https://doi.org/10.1016/j.pnucene.2020.103577.Search in Google Scholar

Lobner, P. (2021). Russia’s Akademik Lomonosov – the first modern floating nuclear power plant (FNPP), Available at: <https://lynceans.org/wp-content/uploads/2021/05/Russia-Akademik-Lomonosov-FNPP-converted.pdf> (Accessed 10 March 2023).Search in Google Scholar

Mays, B., Lommers, L., Yoder, S., and Shahrokhi, F. (2021). Sensitivity of SC-HTGR conduction cooldown to reactor cavity cooling system failure. Nucl. Technol. 208: 1311–1323, https://doi.org/10.1080/00295450.2021.1947664.Search in Google Scholar

Mulder, E.J. and Boyes, W.A. (2020). Neutronics characteristics of a 165 MWth Xe-100 reactor. Nucl. Eng. Des. 357: 110415, https://doi.org/10.1016/j.nucengdes.2019.110415.Search in Google Scholar

Nayak, A.K., Jain, V., Gartia, M.R., Prasad, H., Anthony, A., Bhatia, S.K., and Sinha, R.K. (2009). Reliability assessment of passive isolation condenser system of AHWR using APSRA methodology. Reliab. Eng. Syst. Saf. 94: 1064–1075, https://doi.org/10.1016/j.ress.2008.12.002.Search in Google Scholar

Nguyen, V.P. (2018). China’s planned floating nuclear power Facilities in South China sea: Technical and political challenges. Maritime Issues, Available at: <http://www.maritimeissues.com/environment/china39s-planned-floating-nuclear-power-facilities-in-south-china-sea-technical-and-political-challenges.html>.Search in Google Scholar

NuScale (2020). Reactor coolant system and connecting systems. NuScale standard plant design certification application, Chapter Five, Rev. 5, July 2020. ML20224A493.Search in Google Scholar

Park, H.-S., Kwon, T.-S., Moon, S.-K., Cho, S., Euh, D.-J., and Yi, S.-J. (2017). Contribution of thermal-hydraulic validation tests to the standard design approval of SMART. Nucl. Eng. Technol. 49: 1537–1546, https://doi.org/10.1016/j.net.2017.06.009.Search in Google Scholar

Paydar, A.Z., Mousavi Balgehshiri, S.K., and Zohuri, B. (2022). Advanced reactor concept (ARC) A nuclear energy perspective. J. Mater. Sci. Manuf. Res. 3: 1–6, https://doi.org/10.47363/JMSMR/2022(3)131.Search in Google Scholar

Petrunin, V.V., Fadeev, Yu. P., Pakhomov, A.N., Veshnyakov, K.B., Polunichev, V.I., and Shamanin, I.E. (2019). Conceptual design of small NPP with RITM-200 reactor. Atom. Energy 125: 365–369, https://doi.org/10.1007/s10512-019-00495-4.Search in Google Scholar

Pheil, E. (2019). Fast-spectrum molten-salt reactor, Available at: <https://m.youtube.com/watch?feature=youtu.be&v=pqVt8cxx-44> (Accessed 10 March 2023).Search in Google Scholar

Prasad, M.H., Gaikwad, A.J., Srividya, A., and Verma, A.K. (2011). Failure probability evaluation of passive system using fuzzy Monte Carlo simulation. Nucl. Eng. Des. 241: 1864–1872, https://doi.org/10.1016/j.nucengdes.2011.02.025.Search in Google Scholar

Ruščák, M., Melichar, T., Syblík, J., Frýbort, O., Harut, D., Losa, E., Mareček, M., Mazzini, G., Reungoat, M., Pilát, J., et al.. (2021). Energy well: concept of 20 MW microreactor cooled by molten salts. ASME J. Nucl. Rad. Sci. 7(2): 021302, https://doi.org/10.1115/1.4049715.Search in Google Scholar

Sato, H., Yan, X.L., Tachibana, Y., Yan, X. L., Tachibana, Y., and Kunitomi, K. (2014). GTHTR300 – a nuclear power plant design with 50% generating efficiency. Nucl. Eng. Design 275: 190–196, https://doi.org/10.1016/j.nucengdes.2014.05.004.Search in Google Scholar

Schleicher, R.W., Choi, H., and Rawls, J. (2013). The energy multiplier module: advancing the nuclear fuel cycle through technology innovations. Nucl. Technol. 184: 169–180, https://doi.org/10.13182/NT13-A22313.Search in Google Scholar

Shadrin, A. Yu., Dvoeglazov, K.N., Kascheyev, V.A., Vidanov, V.L., Volk, V.I., Veselov, S.N., Zilberman, B. Ya., Ryabkov, D.V. (2016). Hydrometallurgical reprocessing of BREST-OD-300 mixed uranium-plutonium nuclear fuel. Proc. Chem. 21: 148–155, https://doi.org/10.1016/j.proche.2016.10.021.Search in Google Scholar

Shenoy, A. (2005). GT-MHR overview. Presented to IEEE Subcommittee on qualification, Available at: <http://site.ieee.org/npec-sc2/files/2017/06/SC-2Mgt05-1_Att9-Overview-of-GT-MHR-Reactor.pdf> (Accessed 10 March 2023).Search in Google Scholar

Skoda, R., Fortova, A., Masata, D., Zavorka, J., Lovecky, M., Skarohlid, J., Kolar, F., Vilimova, E., Peltan, T., Burian, O., et al.. (2020). TELPATOR: nuclear district heating solution. 29th International conference nuclear Energy for New Europe (NENE2020), september 7–10, potorož, Slovenia, Available at: <https://arhiv.djs.si/proc/nene2020/pdf/NENE2020_0408.pdf> (Accessed 10 March 2023).Search in Google Scholar

Smith, C.F., (2017). Lead cooled fast reactor. Presentation at Naval Postgraduate School on June 12, 2017, Available at: <https://www.gen-4.org/gif/upload/docs/application/pdf/2017-06/geniv-lfr-cfsmith-final.pdf> (Accessed 10 March 2023).Search in Google Scholar

Solanki, R.B., Kulkarni, H.D., Singh, S., Varde, P.V., and Verma, A.K. (2020). Reliability assessment of passive systems using artificial neural network based response surface methodology. Ann. Nucl. Energy 144: 107487, https://doi.org/10.1016/j.anucene.2020.107487.Search in Google Scholar

Strydom, G., Reitsma, F., Ngeleka, T.P., and Kostadin, I. (2010) The OECD/NEA/NSC PBMR 400 MW coupled neutronics thermal hydraulics transient benchmark: transient results. In: Advances in reactor physics to power the nuclear Renaissance pittsburgh (PHYSOR 2010), Pennsylvania, USA, May 9–14.Search in Google Scholar

Subekti, M., Bakhri, S., and Sunaryo, G.R. (2018). The simulator development for RDE reactor. J. Phys. Conf. 962: 012054, https://doig.org/10.1088/1742-6596/962/1/012054.10.1088/1742-6596/962/1/012054Search in Google Scholar

Teräsvirta, A., Syri, S., and Hiltunen, P. (2020). Small nuclear reactor—nordic district heating case study. Energies 13: 3782, https://doi.org/10.3390/en13153782.Search in Google Scholar

UN (2015). The Paris Agreement, Available at: <https://www.un.org/en/climatechange/paris-agreement> (Accessed 10 March 2023).Search in Google Scholar

USNRC (2022). Aurora – Oklo application, Available at: <https://www.nrc.gov/reactors/new-reactors/col/aurora-oklo.html> (Accessed 10 March 2023).Search in Google Scholar

Venneri, F. (2019). Micro modular reactor (MMR) energy systems. Presentation at IFNEC Workshop, Warsaw, 24. September 2019. Available at: <https://www.ifnec.org/ifnec/upload/docs/application/pdf/2019-09/3-4._usnc_mmr.pdf> (Accessed 10 March 2023).Search in Google Scholar

Wallenius, J., Laurin, D., and Conning, B. (2019). SEALER-UK: a small modular reactor for on-grid power production. In: Proceedings of 39th Annual CNS conference and 43rd CNS/CNA student conference, 23–26 June 2019, Ottawa, Ontario (Canada).Search in Google Scholar

Westinghouse Global Technology Office (2017). Westinghouse eVinciTM Micro reactor, Available at: <https://www.westinghousenuclear.com/Portals/0/new%20plants/evincitm/GTO-0001%20eVinci%20flysheet.pdf> (Accessed 10 March 2023).Search in Google Scholar

World Nuclear Association (2023). Small nuclear power reactors, Available at: <https://www.world-nuclear.org/information-library/nuclear-fuel-cycle/nuclear-power-reactors/small-nuclear-power-reactors.aspx> (Accessed 10 March 2023).Search in Google Scholar

World Nuclear News (2022a). European regulators to cooperate on Nuward SMR licensing, Available at: <https://www.world-nuclear-news.org/Articles/European-regulators-to-cooperate-on-Nuward-licensi> (Accessed 10 March 2023).Search in Google Scholar

World Nuclear News (2022b). Rosatom and Yakutia planning for SHELF-M small nuclear plant. Available at: <https://www.world-nuclear-news.org/Articles/Rosatom-and-Yakutia-planning-for-SHELF-M-small-nuc> 17 June 2022. (Accessed 10 March 2023).Search in Google Scholar

Wu, Z., Lin, D., and Zhong, D. (2002). The design features of the HTR-10. Nucl. Eng. Des. 2018: 25–32, https://doi.org/10.1016/S0029-5493(02)00182-6.Search in Google Scholar

Xu, B. (2016). CNNC’s ACP100 SMR: technique features and progress in China. 13th INPRO dialogue forum on legal and institutional issues in the global deployment of small modular reactors, 18–21 October 2016, Available at: <https://nucleus.iaea.org/sites/INPRO/Pages/df-13.aspx> (Accessed 10 March 2023).Search in Google Scholar

Xujiawang and Wang, M. (2017). Development of Advanced Small modular reactors in China, Available at: <https://www.revistanuclear.es/wp-content/uploads/hemeroteca/380/NE380-06.pdf> (Accessed 10 March 2023).Search in Google Scholar

Zeliang, C., Mi, Y., Tokuhiro, A., Lu, L., and Rezvoi, A. (2020). Integral PWR-type small modular reactor developmental status, design characteristics and passive features: a review. Energies 13: 2898, https://doi.org/10.3390/en13112898.Search in Google Scholar

Zrodnikov, A.V., Toshinsky, G.I., Komlev, O.G., Stepanov, V.S., Klimov, N.N., Kudryavtseva, A.V., and Petrochenko, V.V. (2009). SVBR-100 module-type reactor of the IV generation for regional power industry. Presentation on international conference on fast Reactors and related fuel cycles: challenges and opportunities, IAEA-CN-176-FR09p. 1132, Available at: <https://www.iaea.org/publications/8476/fast-reactors-and-related-fuel-cycles-challenges-and-opportunities-fr09> (Accessed 10 March 2023).Search in Google Scholar

de Zwaan, S.J., Kloosterman, J.L., Linssen, R.J., van der Hagen, T.H.J.J., and van Uitert, G.C. (2007). The U-battery, a conceptual design of a natural circulation cooled nuclear battery for process heat applications. Proceedings of international conference on non-electric applications of nuclear power, 16–19 April 2007, Oarai, Japan, Available at: <https://www-pub.iaea.org/MTCD/Publications/PDF/P_1354_web.pdf> (Accessed 10 March 2023).Search in Google Scholar

Received: 2022-11-18
Published Online: 2023-05-12
Published in Print: 2023-08-28

© 2023 Walter de Gruyter GmbH, Berlin/Boston

Downloaded on 26.9.2025 from https://www.degruyterbrill.com/document/doi/10.1515/kern-2022-0106/html
Scroll to top button