Open Access
| Issue |
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
|
|
|---|---|---|
| Article Number | 06002 | |
| Number of page(s) | 8 | |
| Section | Advanced Modelling and Simulation | |
| DOI | https://doi.org/10.1051/epjconf/202124706002 | |
| Published online | 22 February 2021 | |
- N. E. Stauff et al., “Evaluation of the OECD/NEA/SFR-UAM Neutronics Reactivity Feedback and Uncertainty Benchmarks,” in International Conference on Fast Reactors and Related Fuel Cycles (FR17), Yekaterinburg, Russia, 2017. [Google Scholar]
- B. Lindley et al., “Developments with the WIMS Reactor Physics Code for Whole Core Calculations,” in M&C 2017, Jeju, Korea, April 16-20 2017. [Google Scholar]
- U. Davies, B. Lindley, B. Tollit and E. Shwageraus, “Whole-core validation of the Superphenix reactor using WIMS11 and an investigation into a hybrid RZ-HEX SP3 calculation route,” in M&C2019, Portland, OR, USA, 2019. [Google Scholar]
- J. G. Hosking et al., “Development of a reactor physics uncertainty quantification toolkit for use with the WIMS and MONK codes,” in PHYSOR 2018, Cancun, Mexico, 2018. [Google Scholar]
- K. Mikityuk et al., “ESFR-SMART: new Horizon 2020 project on SFR safety,” in International Conference on Fast Reactors and Related Fuel Cycles (FR17), Yekaterinburg, 2017. [Google Scholar]
- C. Fiorina, I. Clifford, M. Aufiero and K. Mikityuk, “GeN-Foam: A novel OpenFOAM(R) based multi-physics solver for 2D/3D transient analysis of nuclear reactors,” Nuclear Engineering and Design, vol. 294, pp. 24-37, 2015. [Google Scholar]
- E. F. E. Nikitin, “Extension of the reactor dynamics code DYN3D to SFR applications - Part I: Thermal expansion models,” Annals of Nuclear Energy, vol. 119, pp. 382-389, 2018. [Google Scholar]
- R. Calabrese, F. Vettraino, C. Artioli, V. Sobolev and R. Thetford, “Heterogeneous fuels for minor actinides transmutation: Fuel performance codes predictions in the EFIT case study,” Annals of Nuclear Energy, vol. 37 6, pp. 867-874, 2010. [Google Scholar]
- G. Rimpault et al., “The ERANOS code and data system for fast reactor neutronic analysis,” in PHYSOR2002, Seoul, Korea, Oct 7-10, 2002. [Google Scholar]
- R. E. MacFarlane et al., “The NJOY Nuclear Data Processing System Version 2012. LA-UR-12-27079,” Los Alamos National Laboratory, 2012. [Google Scholar]
- J. C. Sublet et al., “CALENDF-2010: User Manual. CEA-R-6277,” 2011. [Google Scholar]
- B. Tollit et al., “Development of a subchannel model within the ANSWERS Software Service WIMS reactor physics code,” in PHYSOR 2018, Cancun, Mexico, Apr 22-26 2018. [Google Scholar]
- K. Mikityuk, “Heat transfer to liquid metal: Review of data and correlations for tube bundles,” Nuclear Engineering and Design, vol. 239, no. 4, pp. 680-7, 2009. [Google Scholar]
- J. Lavarenne et al., “A 2-D correlation to evaluate fuel-cladding gap thermal-conductance in mixed oxide fuel elements for sodium-cooled fast reactors,” in GLOBAL 2019, Seattle, USA, 2019. [Google Scholar]
- E. Fridman, “Current applications of Serpent in the Euratom project ESFR-SMART,” in 8th International Serpent User Group Meeting, Espoo, Finland, 2018. [Google Scholar]
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