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Extension of the DYN3D/ATHLET code system to SFR applications: models description and initial validation
Fridman, E., Nikitin, E., Ponomarev, A., Di Nora, A., Kliem, S., & Mikityuk, K. (2023). Extension of the DYN3D/ATHLET code system to SFR applications: models description and initial validation. Annals of Nuclear Energy, 182, 109619 (10 pp.). https://doi.org/10.1016/j.anucene.2022.109619
Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing - part II: methodology application
Di Nora, V. A., Fridman, E., Nikitin, E., Bilodid, Y., & Mikityuk, K. (2021). Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing - part II: methodology application. Annals of Nuclear Energy, 163, 108541 (9 pp.). https://doi.org/10.1016/j.anucene.2021.108541
On the use of the SPH method in nodal diffusion analyses of SFR cores
Nikitin, E., Fridman, E., & Mikityuk, K. (2015). On the use of the SPH method in nodal diffusion analyses of SFR cores. Annals of Nuclear Energy, 85, 544-551. https://doi.org/10.1016/j.anucene.2015.06.007
Solution of the OECD/NEA neutronic SFR benchmark with Serpent-DYN3D and Serpent-PARCS code systems
Nikitin, E., Fridman, E., & Mikityuk, K. (2015). Solution of the OECD/NEA neutronic SFR benchmark with Serpent-DYN3D and Serpent-PARCS code systems. Annals of Nuclear Energy, 75, 492-497. https://doi.org/10.1016/j.anucene.2014.08.054
A neutronics study for improving the safety and performance parameters of a 3600 MWth Sodium-cooled Fast Reactor
Sun, K., Krepel, J., Mikityuk, K., & Chawla, R. (2013). A neutronics study for improving the safety and performance parameters of a 3600 MWth Sodium-cooled Fast Reactor. Annals of Nuclear Energy, 53, 464-475. https://doi.org/10.1016/j.anucene.2012.10.004
Void reactivity decomposition for the Sodium-cooled Fast Reactor in equilibrium fuel cycle
Sun, K., Krepel, J., Mikityuk, K., Pelloni, S., & Chawla, R. (2011). Void reactivity decomposition for the Sodium-cooled Fast Reactor in equilibrium fuel cycle. Annals of Nuclear Energy, 38(7), 1645-1657. https://doi.org/10.1016/j.anucene.2011.02.018