| Impact of thermal-hydraulic feedback and differential thermal expansion on european sodium-cooled fast reactor core power distribution
Lindley, B., Velarde, F. A., Baker, U., Bodi, J., Cosgrove, P., Charles, A., … Tollit, B. (2023). Impact of thermal-hydraulic feedback and differential thermal expansion on european sodium-cooled fast reactor core power distribution. Journal of Nuclear Engineering and Radiation Science, 9(3), 031301 (13 pp.). https://doi.org/10.1115/1.4056930 |
| Analysis of ESFR decay heat removal systems in protected station blackout
Bodi, J., Ponomarev, A., Bubelis, E., & Mikityuk, K. (2022). Analysis of ESFR decay heat removal systems in protected station blackout. Journal of Nuclear Engineering and Radiation Science, 8(1), 011315 (18 pp.). https://doi.org/10.1115/1.4052190 |
| Coupled neutronics-mechanics analysis method for evaluation of reactivity change due to core distortion in sodium fast reactor
Bodi, J., Ponomarev, A., & Mikityuk, K. (2022). Coupled neutronics-mechanics analysis method for evaluation of reactivity change due to core distortion in sodium fast reactor. Journal of Nuclear Engineering and Radiation Science, 8(1), 011307 (7 pp.). https://doi.org/10.1115/1.4050417 |
| Burn-up dependent modeling of fuel-to-clad gap conductance and temperature predictions for mixed-oxide fuel in the ESFR-SMART core
Lavarenne, J., Bubelis, E., Davies, U., Gianfelici, S., Gicquel, S., Krepel, J., … Van Uffelen, P. (2022). Burn-up dependent modeling of fuel-to-clad gap conductance and temperature predictions for mixed-oxide fuel in the ESFR-SMART core. Journal of Nuclear Engineering and Radiation Science, 8(1), 011306 (11 pp.). https://doi.org/10.1115/1.4050479 |
| Coupled neutronic-therma-hydraulic simulations of the European SFR core
Lindley, B., Álvarez Velarde, F., Bodi, J., Charles, A., Fridman, E., Krepel, J., … Tollit, B. (2022). Coupled neutronic-therma-hydraulic simulations of the European SFR core. In Proceedings international conference on physics of reactors (pp. 625-634). https://doi.org/10.13182/PHYSOR22-37339 |
| Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing - part I: methodology demonstration
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 I: methodology demonstration. Annals of Nuclear Energy, 155, 108183 (9 pp.). https://doi.org/10.1016/j.anucene.2021.108183 |
| Machine learning-based methodology for assessment of Doppler reactivity of sodium-cooled fast reactor
Petrović, Đ., & Mikityuk, K. (2021). Machine learning-based methodology for assessment of Doppler reactivity of sodium-cooled fast reactor. Journal of Nuclear Engineering and Radiation Science, 7(4), 042004 (6 pp.). https://doi.org/10.1115/1.4050216 |
| Validation of TRACE capability to simulate unprotected transients in Sodium Fast Reactor using FFTF LOFWST Test #13
Wang, S., Mikityuk, K., Dorde, P., Zhang, D., Su, G., Qiu, S., & Tian, W. (2021). Validation of TRACE capability to simulate unprotected transients in Sodium Fast Reactor using FFTF LOFWST Test #13. Annals of Nuclear Energy, 164, 108600 (15 pp.). https://doi.org/10.1016/j.anucene.2021.108600 |
| Fuel tap: a simplified breed and burn MSR
de Oliveira, R. G. G., & Hombourger, B. A. (2021). Fuel tap: a simplified breed and burn MSR. In M. Margulis & P. Blaise (Eds.), EPJ web of conferences: Vol. 247. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future (p. 01007 (8 pp.). https://doi.org/10.1051/epjconf/202124701007 |
| The EQL0D fuel cycle procedure and its application to the transition to equilibrium of selected molten salt reactor designs
Hombourger, B., Křepel, J., & Pautz, A. (2020). The EQL0D fuel cycle procedure and its application to the transition to equilibrium of selected molten salt reactor designs. Annals of Nuclear Energy, 144, 107504 (18 pp.). https://doi.org/10.1016/j.anucene.2020.107504 |
| Treatment of the implicit effect in Shark-X
Hursin, M., Pelloni, S., Vasiliev, A., & Ferroukhi, H. (2020). Treatment of the implicit effect in Shark-X. Annals of Nuclear Energy, 138, 107178 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107178 |
| Evaporation of materials from the molten salt reactor fuel under elevated temperatures
Kalilainen, J., Nichenko, S., & Krepel, J. (2020). Evaporation of materials from the molten salt reactor fuel under elevated temperatures. Journal of Nuclear Materials, 533, 152134 (13 pp.). https://doi.org/10.1016/j.jnucmat.2020.152134 |
| Review of Euratom projects on design, safety assessment, R&D and licensing for ESNII/Gen-IV fast neutron systems
Mikityuk, K., Ammirabile, L., Forni, M., Jagielski, J., Girault, N., Horvath, A., … Vasile, A. (2020). Review of Euratom projects on design, safety assessment, R&D and licensing for ESNII/Gen-IV fast neutron systems. EPJ Nuclear Sciences and Technologies, 6, 36 (17 pp.). https://doi.org/10.1051/epjn/2019007 |
| Resonance parameter adjustment in the resolved region based upon an Asymptotic Generalized Linear Least-Squares methodology in conjunction with the Monte Carlo method
Pelloni, S., & Rochman, D. (2020). Resonance parameter adjustment in the resolved region based upon an Asymptotic Generalized Linear Least-Squares methodology in conjunction with the Monte Carlo method. Annals of Nuclear Energy, 145, 107509 (9 pp.). https://doi.org/10.1016/j.anucene.2020.107509 |
| The joint evaluated fission and fusion nuclear data library, JEFF-3.3
Plompen, A. J. M., Cabellos, O., De Saint Jean, C., Fleming, M., Algora, A., Angelone, M., … Žerovnik, G. (2020). The joint evaluated fission and fusion nuclear data library, JEFF-3.3. European Physical Journal A: Hadrons and Nuclei, 56(7), 181 (108 pp.). https://doi.org/10.1140/epja/s10050-020-00141-9 |
| On the prediction of turbulent kinetic energy in channel flow using wall-modeled large eddy simulations
Sayed, M., Hadziabdic, M., Dehbi, A., Niceno, B., & Mikityuk, K. (2020). On the prediction of turbulent kinetic energy in channel flow using wall-modeled large eddy simulations. In AIAA scitech 2020 forum: Vol. 1. AIAA scitech forum. https://doi.org/10.2514/6.2020-1329 |
| Results from a multi-physics numerical benchmark for codes dedicated to molten salt fast reactors
Tiberga, M., de Oliveira, R. G. G., Cervi, E., Blanco, J. A., Lorenzi, S., Aufiero, M., … Rubiolo, P. (2020). Results from a multi-physics numerical benchmark for codes dedicated to molten salt fast reactors. Annals of Nuclear Energy, 142, 107428 (19 pp.). https://doi.org/10.1016/j.anucene.2020.107428 |
| Statistical burnup distribution of moving pebbles in the HTR-PM reactor
Vitullo, F., Krepel, J., Kalilainen, J., Prasser, H. M., & Pautz, A. (2020). Statistical burnup distribution of moving pebbles in the HTR-PM reactor. Journal of Nuclear Engineering and Radiation Science, 6(2), 021108 (14 pp.). https://doi.org/10.1115/1.4044910 |
| Coupled neutronic/thermal-hydraulic hot channel analysis of high power density civil marine SMR cores
Alam, S. B., de Oliveira, R. G. G., Goodwin, C. S., & Parks, G. T. (2019). Coupled neutronic/thermal-hydraulic hot channel analysis of high power density civil marine SMR cores. Annals of Nuclear Energy, 127, 400-411. https://doi.org/10.1016/j.anucene.2018.12.031 |
| Breed-and-burn fuel cycle in molten salt reactors
Hombourger, B., Křepel, J., & Pautz, A. (2019). Breed-and-burn fuel cycle in molten salt reactors. EPJ Nuclear Sciences and Technologies, 5, 15 (10 pp.). https://doi.org/10.1051/epjn/2019026 |
