EPJ Web Conf.
Volume 247, 2021PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
|Number of page(s)||11|
|Section||Monte Carlo Transport|
|Published online||22 February 2021|
- https://myrrha.be/en/about/ [Google Scholar]
- G. Van den Eynde et. al., “An updated core design for the multi-purpose irradiation facility MYRRHA,” Journal of Nucl. Sci,and Tech., 52, pp. 1052–1057 (2015). [Google Scholar]
- X Monte Carlo Team, Los Alamos, “MCNPX “MCNPX 2.4.0. Monte Carlo N-Particle Transport Code System for Multiparticle and High Energy Applications,” CCC-715, LA-CP-02-408, (2002). [Google Scholar]
- A. Stankovskiy, G. Van den Eynde, “Advanced methods for calculations of core burnup, activation of structural materials and spallation products accumulation in accelerator driven systems,” Journal of Science and Technology of Nuclear Installations, (2012), (2012). [Google Scholar]
- E. Malambu Mbala, A. Stankovskiy, “Revised Core Design for MYRRHA –Rev1.6,” SCK•CEN/3958903 Inernal Report, (2014). [Google Scholar]
- P. Romano et. al., “OpenMC: A state-of-the-art Monte Carlo code for research,” Annals of Nuclear Energy, Vol. (82), pp. 90–97, (2015). [Google Scholar]
- W. Boyd et. al., “Multi-group Cross-Section Generation with the OpenMC Monte Carlo Particle Transport Code,” Journal of Nuclear Technology, 205(7), pp. 928–944 (2019). [Google Scholar]
- K. Zhuang et. al., “Development and verification of a model for generation of MSFR few-group homogenized cross-sections based on a Monte Carlo code OpenMC,” Annals of Nuclear Energy, 124, pp. 187–197 (2019). [Google Scholar]
- C. Rabiti et. al., “Phisics: A New Reactor Physics Analysis Toolkit, ” Transactions of the American Nuclear Society, Hollywood, FL, June 26th-30th 2011, Vol. 104, pp. 831–833 (2011). [Google Scholar]
- S. Kalcheva et. al., “Detailed MCNP modeling of BR2 fuel with azimuthal variation,” Journal of Nuclear Technology, 158(1), pp. 36–55 (2007). [Google Scholar]
- C. J. Werner (editor), “MCNP Users Manual –Code Version 6.2,” LA-UR-17-29981 (2017). [Google Scholar]
- Y. Molla, “OpenMC modeling of the critical MYRRHA configuration: An emphasis in cross-section homogenization,” LUT University, School of Energy Systems, MSc thesis BA10A0202 (2019). [Google Scholar]
- L. Cai, “Condensation and homogenization of cross sections for the deterministic transport codes with Monte Carlo method: Application to the GEN-IV fast neutron reactors,” Université Paris Sud –Paris XI, 2014PA112280, (2014). [Google Scholar]
- Y. Wang et. al., “Krylov solvers preconditioned with the Low-Order Red-Black algorithm for the PN hybrid FEM for the Instant code,” Proceedings of International Conference of Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Rio de Janeiro, Brazil, May 8th-12th 2011 (2011). [Google Scholar]
- E. Lewis et. al., “Variational Nodal Formulation for the spherical harmonics equation,” Journal of Nucl. Sci. and Eng., 122, (1996). [Google Scholar]
- J. Ortensi et. al., “A Newton solution for the Superhomogenization method: The PJFNK-SPH,” Annals of Nuclear Energy, 111, pp. 579–594 (2018). [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.