Nuclear Engineering and Technology

  • 제56권3호
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  • Pages.803-811
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  • 2024
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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PASTELS project - overall progress of the project on experimental and numerical activities on passive safety systems

  • 투고 : 2023.05.30
  • 심사 : 2023.08.11
  • 발행 : 2024.03.25
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초록

Nuclear accidents such as Fukushima Daiichi have highlighted the potential of passive safety systems to replace or complement active safety systems as part of the overall prevention and/or mitigation strategies. In addition, passive systems are key features of Small Modular Reactors (SMRs), for which they are becoming almost unavoidable and are part of the basic design of many reactors available in today's nuclear market. Nevertheless, their potential to significantly increase the safety of nuclear power plants still needs to be strengthened, in particular the ability of computer codes to determine their performance and reliability in industrial applications and support the safety demonstration. The PASTELS project (September 2020-February 2024), funded by the European Commission "Euratom H2020" programme, is devoted to the study of passive systems relying on natural circulation. The project focuses on two types, namely the SAfety COndenser (SACO) for the evacuation of the core residual power and the Containment Wall Condenser (CWC) for the reduction of heat and pressure in the containment vessel in case of accident. A specific design for each of these systems is being investigated in the project. Firstly, a straight vertical pool type of SACO has been implemented on the Framatome's PKL loop at Erlangen. It represents a tube bundle type heat exchanger that transfers heat from the secondary circuit to the water pool in which it is immersed by condensing the vapour generated in the steam generator. Secondly, the project relies on the CWC installed on the PASI test loop at LUT University in Finland. This facility reproduces the thermal-hydraulic behaviour of a Passive Containment Cooling System (PCCS) mainly composed of a CWC, a heat exchanger in the containment vessel connected to a water tank at atmospheric pressure outside the vessel which represents the ultimate heat sink. Several activities are carried out within the framework of the project. Different tests are conducted on these integral test facilities to produce new and relevant experimental data allowing to better characterize the physical behaviours and the performances of these systems for various thermo-hydraulic conditions. These test programmes are simulated by different codes acting at different scales, mainly system and CFD codes. New "system/CFD" coupling approaches are also considered to evaluate their potential to benefit both from the accuracy of CFD in regions where local 3D effects are dominant and system codes whose computational speed, robustness and general level of physical validation are particularly appreciated in industrial studies. In parallel, the project includes the study of single and two-phase natural circulation loops through a bibliographical study and the simulations of the PERSEO and HERO-2 experimental facilities. After a synthetic presentation of the project and its objectives, this article provides the reader with findings related to the physical analysis of the test results obtained on the PKL and PASI installations as well an overall evaluation of the capability of the different numerical tools to simulate passive systems.

키워드

과제정보

The PASTELS project has received funding from the Euratom research and training programme 2019-2020 under grant agreement No 945275. This text reflects only the author's view and the Commission is not responsible for any use that may be made of the information contained therein. The PASTELS project idea has also obtained the NUGENIA label on 23/09/2019 (Certificate number: 2019NUG0076) prior to the submission of the project to the European Commission.

참고문헌

  1. V.G. Asmolov, I.N. Gusev, V.R. Kazanskiy, V.P. Povarov, D.B. Statsura, New generation first-of-the kind unit - VVER-1200 design features, Nuclear Energy and Technology 3 (4) (2017) 260-269. https://doi.org/10.1016/j.nucet.2017.10.003
  2. Balendra Sutharshan, Meena Mutyala, Ronald P. Vijuk, Alok Mishra, The AP1000TM reactor: passive safety and modular design, Energy Procedia 7 (2011).
  3. Ji Xing, Daiyong Song, Yuxiang Wu, HPR1000: advanced pressurized water reactor with active and passive safety, Engineering 2 (2016) 79-87. https://doi.org/10.1016/J.ENG.2016.01.017
  4. IAEA, Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants", 2009. IAEA-Tecdoc-1624.
  5. IAEA, Natural Circulation Phenomena and Modelling for Advanced Water Cooled Reactors", 2012. IAEA-Tecdoc-1677.
  6. W. Kohler, O. Herbst, W. Kastner, Thermal-hydraulic behavior of a safety condenser, Proceedings of 1994 New Trends In Nuclear System Thermohydraulics 1 (1994) 609-614. Pisa, Italy, May 30 - June 2.
  7. M. Polidori, P. Meloni, C. Lombardo, A. Achilli, C. Congiu, G. Cattadori, Test Campaign and RELAP5 Post-Test Analysis on the Bayonet Tube HERO-2 Component, Proceeding of 2019 International Congress on Advances in nuclear Power Plants (ICAPP'19), Juan-les-Pins, France, 2019. May 12-15.
  8. A. Achilli, G. Cattadori, R. Ferri, M. Rigamonti, F. Bianchi, P. Meloni, PERSEO Project: Experimental Facility Set-Up and RELAP5 Code Calculations", Proceeding of 2nd EMSI and 40th European Two-Phase Flow Group Meeting, Stockholm, Sweden, 2002. June 10-13.
  9. R. Prea, P. Fillion, L. Matteo, G. Mauger, A. Mekkas, CATHARE-3 V2.1 : the new industrial version of the CATHARE code, Proceedings of 2020 International Topical Meeting on Advances in Thermal Hydraulics (ATH'2020), EDF Lab (2020) 730-742. Palaiseau, France, October 23-25.
  10. G. Lerchl, H. Austregesilo, A. Langenfeld, P.J. Schoffel, D. von der Cron, F. Weyermann, ATHLET 3.2 User's Manual", GRS-P-1/Vol. 1 Rev. 8. Gesellschaft fur Anlagen-und Reaktorsicherheit (GRS) gGmbH, February 2019.
  11. J. Wang, X. Li, C. Allison, J. Hohorst, Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application", Woodhead Publishing, Oxford, 2020.
  12. M. Hanninen, J. Ylijoki, The One-Dimensional Separate Two-phase Flow Model of APROS, Espoo 2008, VTT Research Notes 2443, VTT Tiedotteita, 2008, p. 61.
  13. C.D. Fletcher, R.R. Schultz, RELAP5/MOD3.3 Code Manual", NUREG/CR-5535, Idaho National Engineering Laboratory, January, 2002. INEL-95/174.
  14. United States Nuclear Regulatory Commission, TRACE V5.0 Theory Manual: Field Equations, Solution Methods, and Physical Models", ML071000097, United States Nuclear Regulatory Commission, Washington, DC, USA, 2012.
  15. A. Guelfi, D. Bestion, M. Boucker, P. Boudier, P. Fillion, M. Grandotto, J.-M. Herard, E. Hervieu, P. Peturaud, NEPTUNE -A new software platform for advanced nuclear thermal-hydraulics, Nuclear Science and Engineering 156 (2007) 281-324. https://doi.org/10.13182/NSE05-98
  16. ANSYS Fluent User's Guide, Release 18.0, ANSYS, Inc., Southpointe 2600, ANSYS Drive, Canonsburg, PA 15317, 2017. January.
  17. P. Chatelard, N. Reinke, S. Arndt, S. Belon, L. Cantrel, L. Carenini, K. Chevalier-Jabet, F. Cousin, J. Eckel, F. Jacq, C. Marchetto, C. Mun, L. Piar, ASTEC V2 severe accident integral code main features, current V2.0 modelling status, perspectives, Nuclear Engineering and Design 272 (2014) 119-135. https://doi.org/10.1016/j.nucengdes.2013.06.040
  18. L.L. Humphries, et al., MELCOR computer code manuals, Primer and Users' Guide, Version 2.2.14959, SAND2019-12536 O, October, in: L.L. Humphries, et al. (Eds.), MELCOR Computer Code Manuals, 1, 2019. Vol. 2: Reference Manual, Version 2.2.14959, SAND2019-12537 O, October (2019).
  19. 38 PASTELS project, Deliverable D2.1: Bibliographic Research on the Phenomena Related to the Natural Circulation in Closed Loop, 2021.
  20. 38 PASTELS project, Deliverable D2.2: Description of HERO-2 Facility and Simulations, 2022.
  21. C. Herer, L. Vyskocil, A. Kecek, Natural Circulation HERO-2 Experiment Simulations for the EU Funded PASTELS Project, International Conference on Topical Issues in Nuclear Installation Safety: Strengthening Safety of Evolutionary and Innovative Reactor Designs, 18-21 October, 2022 (Vienna, Austria).
  22. K. Umminger, L. Dennhardt, S. Schollenberger, B. Schoen, Integral tTest acility PKL: experimental PWR accident investigation, Science and Technology of Nuclear Installations 2012 (2012) 16. Article ID 891056.
  23. 38 PASTELS project, Deliverable D3.1: PKL & SACO Technical Description & Design Review Report, 2020.
  24. Stephan Leyer, Michael Wich, The Integral Test Facility Karlstein. Science and Technology of Nuclear Installations, 2012, https://doi.org/10.1155/2012/43937.
  25. 38 PASTELS project, Deliverable D3.2: PKL-SACO Phase 1-experiments, 2023. to be published in early.
  26. 38 PASTELS project, Deliverable D3.3: Summary of P1 Pre and Post-test Calculations, 2023. to be published in early.
  27. V. Riikonen Kouhia, O.-P. Kauppinen, J. Telkka, J. Hyvarinen, PASI - a test facility for research on passive heat removal, Nuclear Engineering and Design 383 (2021) 1-12, https://doi.org/10.1016/j.nucengdes.2021.111417. Article 111417.
  28. 38 PASTELS project, Deliverable D4.2, PASI facility description for PASTELS, 2021.
  29. 38 PASTELS project, Deliverable D4.1, PASI test specification, 2021.
  30. 38 PASTELS project, Deliverable D4.3: PASI Pre-tests Analysis Results", 2022.
  31. M. Montout, C. Herer, I. Gomez-Garcia-Torano, Joonas Telkka, M. Polidori, PASTELS - PAssive systems: simulating the thermalhydraulics with ExperimentaL studies, in: The 19th International Topical Meeting On Nuclear Reactor Thermal Hydraulics (NURETH-19), 2022. Brussels, Belgium, March 6 - 11.
  32. Kecek Adam, Video Competition IT Presented at the 19th International Topical Meeting On Nuclear Reactor Thermal Hydraulics (NURETH-19), 2022. Brussels, Belgium, March 6 - 11.
  33. Omar S. Al-Yahia, Ivor Clifford, Konstantin Nikitin, Hakim Ferroukhi, Parametric study on the modeling of the open passive containment cooling system (CWC), in: The 13th International Topical Meeting On Nuclear Reactor Thermal-Hydraulics, Operation And Safety (NUTHOS 13), 2022. Taichung, Taiwan, September 5-10.
  34. V. Tulkki, M. Montout, M. Bourgeois, Ensuring Safety with Passive Systems-ELSMOR, PASTELS and NUCOBAM Projects, Invited Paper + Poster on PASTELS project, FISA 2022 Conference, May 30-June 6, 2022 (Lyon, France).
  35. S. Cevikalp Usta, M. Buck, J. Starflinger, Evaluation and Validation of ATHLET Code for Bayonet Heat Exchangers, Poster for Student's Competition, FISA 2022 Conference, May 30-June 6, 2022 (Lyon, France).
  36. M. Montout, et al., Progress towards simulation of passive safety systems, SNETP FORUM 2021 -Towards innovative R&D in civil nuclear fission 3 (2021). February.
  37. S. Cevikalp Usta, M. Buck, J. Starflinger, Validation of ATHLET for Bayonet Heat Exchangers with Natural Convection Heat Transfer, Young Scientist Workshop At Kerntechnik, 2022. June 21-22, 2022, Leipzig, Germany.
  38. References [1] to [8] concerning the PASTELS project deliverables are public documents and can be downloaded from the official PASTELS project website: https://www.pastels-h2020.eu/