Open Access
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
Article Number 02030
Number of page(s) 10
Section Core Analysis Methods
Published online 22 February 2021
  1. B. A. Lindley, T. D. Newton, J. G. Hosking, P. N. Smith, D. J. Powney, B. Tollit, and P. J. Smith. “Release of WIMS10: A Versatile Reactor Physics Code for Thermal and Fast Systems.” In Proceedings of ICAPP 2015, Nice, France (May 2015). [Google Scholar]
  2. P. K. Hutt, N. Gaines, M. McEllin, R. J. White, and M. J. Halsall. “The UK Core Performance Code Package.” Nuclear Energy, volume 30, No.5, pp. 291–298 (1991). [Google Scholar]
  3. P. Bryce, G. Hosking, M. Knight, B. Lindley, D. Powney, C. Schneidesch, N. Slosse, and T. Taylor. “Validation of the WIMS/PANTHER Embedded Supercell Method.” In PHYSOR2020: Transition to a Scalable Nuclear Future, Cambridge UK. American Nuclear Society (April 2020). [Google Scholar]
  4. M. Knight, P. Bryce, and S. Hall. “WIMS/PANTHER Analysis of UO2/MOX Cores using Embedded Supercells.” Nuclear Technology, volume 183(3), pp. 398–408 (2013). [Google Scholar]
  5. M. Knight, P. Bryce, and T. Taylor. “Use of a Line of Pincells to Refine Discontinuity Factors and Group Structure for MOX/UO2 Modelling in the Embedded Supercell Methodology.” In Topical Meeting on Reactor Physics, PHYSOR 2016, Sun Valley, Idaho, USA. American Nuclear Society (April 2016). [Google Scholar]
  6. S. Hall. “The Development of a Nodal Method for the Analysis of PWR Cores with Advanced Fuels.” (May 2013). PhD Thesis, Imperial College London. [Google Scholar]
  7. T. Bahadir, S.-Ö. Lindahl, and S. P. Palmtag. “SIMULATE-4 Multi-group Nodal Code with Microscopic Depletion Model.” In ANS Topical Meeting in Mathematics and Computation, Avignon, France (2005). [Google Scholar]
  8. A.-M. Baudron and J.-J. Lautard. “MINOS: A Simplified Pn Solver for Core Calculation.” Nuclear Science and Engineering, volume 155(2), pp. 250–263 (2007). [Google Scholar]
  9. C. Beckert and U. Grundmann. “Development and Verification of a Nodal Approach for Solving the Multigroup SP3 Equations.” Annals of Nuclear Energy, volume 35, pp. 75–86 (2008). [Google Scholar]
  10. T. Downar, Y. Xu, V. Seker, and N. Hudson. “Theory Manual for the PARCS Kinetics Core Simulator Module.” Technical report, Department of Nuclear Engineering and Radiological Sciences, University of Michigan (2010). [Google Scholar]
  11. S. Choi, K. Smith, and D. Lee. “Investigation of diffusion coefficient calculation methods for two-step LWR analysis.” In Topical Meeting on Reactor Physics, PHYSOR 2016, Sun Valley, Idaho, USA. American Nuclear Society (May 2016). [Google Scholar]
  12. Z. Liu, K. Smith, and B. Forget. “A Cumulative Migration Method for Computing Rigorous Transport Cross Sections and Diffusion Coefficients for LWR Lattices with Monte Carlo.” In Topical Meeting on Reactor Physics, PHYSOR 2016, Sun Valley, Idaho, USA. American Nuclear Society (May 2016). [Google Scholar]
  13. J. Leppänen, M. Pusa, T. Viitanen, V. Valtavirta, and T. Kaltiaisenaho. “The Serpent Monte Carlo Code: Status, Development and Applications in 2013.” Annals of Nuclear Energy, volume 82, pp. 142–150 (2015). [Google Scholar]
  14. N. Z. Cho. “KAIST/NurapT: Benchmark Problem 1A: MOX Fuel-Loaded Small PWR Core (MOX Fuel with Zoning).” (2000). URL [Google Scholar]
  15. A. T. Godfrey. “VERA Core Physics Benchmark Progression: Problem Specifications.” Technical Report CASL-U-2012-0131-004, CASL (Revision 4, August 2014). [Google Scholar]

Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.

Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.

Initial download of the metrics may take a while.