Open Access
| Issue |
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
|
|
|---|---|---|
| Article Number | 13004 | |
| Number of page(s) | 8 | |
| Section | Fuel Cycle and Scenarios | |
| DOI | https://doi.org/10.1051/epjconf/202124713004 | |
| Published online | 22 February 2021 | |
- Krepel J, Losa E. Closed U-Pu and Th-U cycle in sixteen selected reactors: Comparison of major equilibrium features. Annals of Nuclear Energy. 2019; vol: 128; pp: 341–57. [Google Scholar]
- Fiorini GL, Vasile A. European Commission - 7th framework programme: The collaborative project on European sodium fast reactor (CP ESFR). Nuclear Engineering and Design. 2011; vol: 241; pp: 3461–9. [Google Scholar]
- Varaine F, Marsault P, Chenaud MS, Bernardin B, Conti A, Sciora P, et al. Pre-conceptual design study of ASTRID core. Proceedings of ICAPP 2012, Chiacago, USA; vol: 1; pp: 572–9. [Google Scholar]
- Mikityuk K., et al. “ESFR - SMART: new Horizon - 2020 project on SFR safety.” In FR17 International Conference. Yekaterinburg, Russia (2017). [Google Scholar]
- Kim YI, Hill R, Grimm K, Rimpault G, Newton T, Li ZH, et al. BN-600 full MOX core benchmark analysis. Proceedings of PHYSOR 2004; pp: 249–61. [Google Scholar]
- Krepel J, Pelloni S, Bortot S, Panadero A, Mikityuk K. Mapping of Sodium Void Worth and Doppler Effect for Sodium-cooled Fast Reactor. Proceedings of ICAPP 2015; Nice, France. [Google Scholar]
- Tomic G, Krepel J. ESFR-SMART core burnup calculation on radially infinite lattice with Monte-Carlo code. Proceedings of ICAPP 2019, Juan-les-pins, France. [Google Scholar]
- Rineiski A, Meriot C, Marchetti M, Krepel J, Iket KIT, Nord C, et al. Core Safety Measures in ESFR-SMART. PHYSOR 2018, Cancun, Mexico. pp: 3401–12. [Google Scholar]
- Leppanen J. Serpent – a Continuous-energy Monte Carlo Reactor Physics Burnup Calculation Code; VTT Technical Research Centre of Finland. (June 18, 2015). [Google Scholar]
- Sisl V, Frybort J, Krepel J, Division S. Mixed LEU - Th Initial Core and Running - In Phase for the HTR - PM Reactor. Proceedings of HTR 2018; Warsaw, Poland. [Google Scholar]
- Krepel J, Pelloni S, Mikityuk K, Coddington P. EQL3D: ERANOS based equilibrium fuel cycle procedure for fast reactors. Annals of Nuclear Energy. 2009; vol: 36; pp: 550–61. [Google Scholar]
- Davies U., as al. Evaluation of the ESFR end of cycle state and detailed analysis of spatial distributions of reactivity coefficients. PHYSOR2020, Cambridge, United Kingdom, March 29th-April 2nd, 2020. [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.