Open Access
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
Article Number 02010
Number of page(s) 8
Section Core Analysis Methods
Published online 22 February 2021
  1. O. C. Zienkiewicz, R. L. Tayler, “The Finite Element Method. Vol. 1: Basic Formulation and Linear Problems”, 4th edition, MacGraw-Hill Book Company, 1994 [Google Scholar]
  2. A. Hebert, “A Raviart–Thomas–Schneider solution of the diffusion equation in hexagonal geometry”, Annals of Nuclear Energy 35 (2008) 363–376. [Google Scholar]
  3. Y. Wang, M. Bangerth, and J. Ragusa, “Three-dimensional h-adaptivity for the multigroup neutron diffusion equations”, Progr. Nucl. Energy, 2009. [Google Scholar]
  4. S. González-Pintor, D. Ginestar, and G. Verdú, “High order finite element method for the Lambda Modes problem on hexagonal geometry”, Annals of Nuclear Energy 36 (2009) 1450–1462. [Google Scholar]
  5. C. Baker, A. Buchan, C. Pain, B. Tollit, M. Goffin, S. Merton, and P. Warner, “Goal based mesh adaptivity for fixed source radiation transport calculations”, Annals of Nuclear Energy, vol. 55, no. 0, pp. 169 –183, 2013. [Google Scholar]
  6. Y. Saad, “Iterative Methods for Linear Systems”, PWS Publishing, Boston, 1996. [Google Scholar]
  7. J. Ortensi, “OECD/NEA Coupled Neutronic/Thermal-Fluids Benchmark of the MHTGR-350 MW Core Design: Results for Phase-I Exercise 1”, NEA/OECD, 2018. [Google Scholar]
  8. H. G. Joo, D. Barber, G. Jiang, T. J. Downar, “PARCS, A Multi-Dimensional Two-Group Reactor Kinetics Code Based on the Nonlinear Analytic Nodal Method,” PU/NE-98-26, Sept. 1998 [Google Scholar]
  9. A. Hébert, “TRIVAC, a Modular Diffusion Code for Fuel Management and Design Applications”, Nucl. J. of Canada, 1 No. 4 (1987) 325. [Google Scholar]
  10. A. Seubert, K. Velkov, “Stand-alone Neutronic Solutions of the OECD/NEA MHTGR-350 MW Core Design Benchmark”, Jahrestagung Kerntechnik 2014, Frankfurt a. M., Germany. [Google Scholar]
  11. F. Varaine et al., “Pre-conceptual design study of ASTRID core”, Proceedings of ICAPP ’12, Chicago (USA), June 24-28, 2012, Paper 12173. [Google Scholar]
  12. F. Gabrielli, A. Rineiski, B. Vezzoni, W. Maschek, C. Fazio, M. Salvatores, “ASTRID-like Fast Reac-tor Cores for Burning Plutonium and Minor Actinides”, Energy Procedia 71 (2015) 130 –139. [Google Scholar]
  13. M. Massone, F. Gabrielli, A. Rineiski, “SIMMER Extension for Multigroup Energy Structure Search using Genetic Algorithm”, M&C 2017 -International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, Jeju, Korea, April 16-20, 2017, on USB (2017). [Google Scholar]
  14. J. J. Casal, R. J. Stamm’ler, E. A. Villarino, A. A. Ferri, “HELIOS: Geometric Capabilities of a New Fuel Assembly Program”, International Topical Meeting on Advances in Mathematics and Computa-tion, Pittsburgh (USA), 1991. [Google Scholar]
  15. A. Wielenberg, L. Lovasz, P. Pandazis, A. Papukchiev, L. Tiborcz, P. Schöffel, C. Spengler, M. Sonnenkalb, A. Schaffrath, “Recent improvements in the system code package AC2 2019 for the safety analysis of nuclear reactors”, Nuclear Engineering and Design 354 (2019) 110211. [Google Scholar]

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