Open Access
Issue |
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
|
|
---|---|---|
Article Number | 04006 | |
Number of page(s) | 8 | |
Section | Monte Carlo Transport | |
DOI | https://doi.org/10.1051/epjconf/202124704006 | |
Published online | 22 February 2021 |
- “CASL - a DOE Energy Innovation Hub for Modeling and Simulation of Nuclear Reactors” The Consortium for Advanced Simulation of Light Water Reactors, https://www.casl.gov/. [Google Scholar]
- L. Mercatali, et. al. “The EC McSAFE Project: High Performance Monte Carlo Methods for Safety Demonstration – Status and Perspectives” International Multi-Physics Validation Workshop, North Carolina State University, Raleigh, USA, June 14-15 (2018). [Google Scholar]
- U. Imke, et. al. “Validation of the Subchannel Code SUBCHANFLOW Using the NUPEC PWR Tests (PSBT)”. Science and Technology of Nuclear Installations, 2012. [Google Scholar]
- Leppänen, J., et al. (2015) “The Serpent Monte Carlo code: Status, development and applications in 2013.” Ann. Nucl. Energy, 82, pp. 142–150, (2015). [Google Scholar]
- Valtavirta, V. “Internal Neutronics-temperature coupling in Serpent 2 -- Reactivity differences resulting from choice of material property correlations.” In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013. [Google Scholar]
- M. García, et al., Advanced Modelling Capabilities for Pin-level Subchannel Analysis of PWR and VVER Reactors, in: 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), 2019. [Google Scholar]
- D. Ferraro et al. “Serpent/SUBCHANFLOW pin-by-pin coupled transient calculations for a PWR minicore” Ann. Nucl. Energy, 137, (2020). [Google Scholar]
- T. Lötsch et al “Proposal of a Benchmark on core burnup follow calculations for a VVER-1000 reactor core” Proceedings of the 19th Symposium of AER on VVER Reactor Physics and Reactor Safety (2009, Varna, Bulgaria) [Google Scholar]
- T. Lötsch et al “Solutions for the task 1 and task 2 of the benchmark for core burnup calculations for a VVER-1000 reactor”, Proceedings of the 21th Symposium of AER on VVER Reactor Physics and Reactor Safety (2011, Dresden, Germany). [Google Scholar]
- T. Lötsch et al. “Corrections and additions to the proposal of a benchmark for core burnup calculations for a WWER-1000 reactor” Proceedings of the 20th symposium of atomic energy research, (p. 790). Hungary: Kiadja and KFKI Atomenergia Kutatointezet (2010). [Google Scholar]
- Serpent developer team, Serpent Wiki on-line user Manual for Serpent 2, http://serpent.vtt.fi/mediawiki/index.php/Main_Page [Google Scholar]
- Ferraro et al. “Foreseen capabilities, bottlenecks identification and potential limitations of serpent mc transport code in large-scale full 3-D burnup calculations” 26th International Conference on Nuclear Engineering, ICONE 2018; London; United Kingdom (2018). [Google Scholar]
- Leppänen, J., & Isotalo, A. “Burnup calculation methodology in the Serpent 2 Monte Carlo code”. In Proceedings: International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012. ANS Vol. 2, pp. 924–935 (2012). [Google Scholar]
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