Nuclear Engineering and Technology

  • 제49권6호
  • /
  • Pages.1339-1345
  • /
  • 2017
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지
DOI QR코드

DOI QR Code

CTF/DYN3D multi-scale coupled simulation of a rod ejection transient on the NURESIM platform

  • Perin, Yann (Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH) ;
  • Velkov, Kiril (Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH)
  • 투고 : 2017.05.23
  • 심사 : 2017.07.18
  • 발행 : 2017.09.25
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

In the framework of the EU funded project NURESAFE, the subchannel code CTF and the neutronics code DYN3D were integrated and coupled on the NURESIM platform. The developments achieved during this 3-year project include assembly-level and pin-by-pin multiphysics thermal hydraulics/neutron kinetics coupling. In order to test this coupling, a PWR rod ejection transient was simulated on a MOX/UOX minicore. The transient is simulated using two different models of the minicore. In the first simulation, both codes model the core with an assembly-wise resolution. In the second simulation, a pin-by-pin fuel-centered model is used in CTF for the central assembly, and a pin power reconstruction method is applied in DYN3D. The analysis shows the influence of the different models on global parameters, such as the power and the average fuel temperature, but also on local parameters such as the maximum fuel temperature.

키워드

참고문헌

  1. B. Chanaron, C. Ahnert, N. Crouzet, V. Sanchez, N. Kolev, O. Marchand, S. Kliem, A. Papukchiev, Advanced multi-physics simulation for reactor safety in the framework of the NURESAFE project, Ann. Nucl. Energy 84 (2015).
  2. U. Rohde, The reactor dynamics code DYN3D-models, validation and applications, Prog. Nucl. Energy 89 (2016).
  3. U. Grundmann, F. Hollstein, A two-dimensional intranodal flux expansion method for hexagonal geometry, Nucl. Sci. Eng. 133 (1999).
  4. C. Beckert, U. Grundmann, Development and verification of a nodal approach for solving the multigroup SP3 equations, Ann. Nucl. Energy 35 (2008).
  5. S. Duerigen, E. Fridman, The simplified P3 approach on a trigonal geometry of the nodal reactor code DYN3D, Kerntechnik 77 (2012) 226-229. https://doi.org/10.3139/124.110247
  6. A. Gomez-torres, V. Sanchez-espinoza, S. Kliem, A. Gommlich, Implementation of a fast running full core pin power reconstruction method in DYN3D, Nucl. Eng. Des. 274 (2014).
  7. U. Grundmann, S. Kliem, Analyses of the OECD main steam line break benchmark with the DYN3D and ATHLET codes, Nucl. Technol. 142 (2003).
  8. U. Grundmann, S. Kliem, U. Rohde, Analysis of the boiling water reactor turbine trip benchmark with the codes DYN3D and ATHLET/DYN3D, Nucl. Sci. Eng. 148 (2004).
  9. M. Avramova, COBRA-TF Development, Qualification, and Application to Light Water Reactor Analysis, Tech. rep., The Pennsylvania State University, 2003.
  10. R. Salko, M. Avramova, CTF Pre-processor User's Manual, Tech. rep., The North Carolina State University, 2016.
  11. R. Salko, T. Blyth, C. Dances, J. Magedanz, C. Jernigan, J. Kelly, A. Toptan, M. Gergar, C. Gosdin, M. Avramova, S. Palmtag, J. Gehin, CTF Validation and Verification, Tech. rep., The North Carolina State University, 2016.
  12. R. Salko, A. Wysocki, M. Avramova, A. Toptan, N. Porter, T. Blyth, C. Dances, A. Gomez, C. Jernigan, J. Kelly, CTF Theory Manual, Tech. rep., The North Carolina State University, 2016.
  13. R. Salko, et al., CTF Parallel Performance Improvements," in "Proceedings of 2016 ANSWinter Meeting and Nuclear Technology Expo, Las Vegas, USA, 2016.
  14. C. Chauliac, J.-M. Aragones, D. Bestion, D. Cacuci, N. Crouzet, F.-P. Weiss, M. Zimmermann, NURESIM aAS A European simulation platform for nuclear reactor safety: multi-scale and multi-physics calculations, sensitivity and uncertainty analysis, Nucl. Eng. Des. 241 (2011).
  15. A. Grahn, et al., Coupling of the 3D neutron kinetic core model DYN3D with the CFD software TRIO-U and simulation of a MSLB scenario, Nucl. Eng. Des. 315 (2017).
  16. S. Kliem, Y. Kozmenkov, J. Hadek, Y. Perin, F. Fouquet, F. Bernard, A. Sargeni, D. Cuervo, A. Sabater, S. Sanchez-cervera, N. Garcia-herranz, O. Zerkak, H. Ferroukhi, P. Mala, Testing the NURESIM platform on a PWR main steam line break benchmark, Nucl. Eng. Des. (2017). In press (available online).
  17. Y. Perin, J. Jimenez, Application of the best-estimate plus uncertainty approach on a BWR ATWS transient using the NURESIM European code platform, Nucl. Eng. Des. (2017). In press (available online).
  18. T. Kozlowski, T. Downar, OECD/NEA and U.S. NRC PWR MOX/UO2 Core Transient Benchmark, Final Specifications, Tech. rep., OECD/NEA, 2003.
  19. R. Sanchez, APOLLO 2: a user oriented, portable modular code for multi-group transport assembly calculations, Nucl. Sci. Eng. 100 (1988).

피인용 문헌

  1. COUPLED TRANSIENT ANALYSIS OF A CORE WITH FUEL ASSEMBLY BOWING WITH A HYBRID CTF/DYN3D MODEL vol.247, pp.None, 2021, https://doi.org/10.1051/epjconf/202124706036