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Aerodynamic study of a Hyperloop pod equipped with compressor to overcome the Kantrowitz limit
Bizzozero, M., Sato, Y., & Sayed, M. A. (2021). Aerodynamic study of a Hyperloop pod equipped with compressor to overcome the Kantrowitz limit. Journal of Wind Engineering and Industrial Aerodynamics, 218, 104784 (16 pp.). https://doi.org/10.1016/j.jweia.2021.104784
Evaluation of the ESFR end of cycle state and detailed analysis of spatial distributions of reactivity coefficients
Davies, U., Margulis, M., Shwageraus, E., Fridman, E., Garcia-Herranz, N., Jimenez-Carrascosa, A., … Krepel, J. (2021). Evaluation of the ESFR end of cycle state and detailed analysis of spatial distributions of reactivity coefficients. 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. 02001 (10 pp.). https://doi.org/10.1051/epjconf/202124702001
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
ESFR smart project conceptual design of in-vessel core catcher
Guidez, J., Gerschenfeld, A., Bodi, J., Mikityuk, K., Alvarez-Velarde, F., Romojaro, P., & Diaz-Chiron, U. (2021). ESFR smart project conceptual design of in-vessel core catcher. 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. 01002 (7 pp.). https://doi.org/10.1051/epjconf/202124701002
Insights on the interaction of serpentine channels and gas diffusion layer in an operating polymer electrolyte fuel cell: numerical modeling across scales
Khatoonabadi, M., Safi, M. A., Prasianakis, N. I., Roth, J., Mantzaras, J., Kirov, N., & Büchi, F. N. (2021). Insights on the interaction of serpentine channels and gas diffusion layer in an operating polymer electrolyte fuel cell: numerical modeling across scales. International Journal of Heat and Mass Transfer, 181, 121859 (13 pp.). https://doi.org/10.1016/j.ijheatmasstransfer.2021.121859
Mapping of sodium void effect and Doppler constant in ESFR-smart core with Monte Carlo code serpent and deterministic code ERANOS
Krepel, J., & Raffuzzi, V. (2021). Mapping of sodium void effect and Doppler constant in ESFR-smart core with Monte Carlo code serpent and deterministic code ERANOS. 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. 13004 (8 pp.). https://doi.org/10.1051/epjconf/202124713004
Neutronic modelling of the FFTF control rod worth measurements with diffusion codes
Nikitin, E., Fridman, E., Mikityuk, K., Radman, S., & Fiorina, C. (2021). Neutronic modelling of the FFTF control rod worth measurements with diffusion codes. 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. 10017 (8 pp.). https://doi.org/10.1051/epjconf/202124710017
Addressing challenges in nuclear data adjustment techniques using integral experiments based upon uranium solution thermal systems
Pelloni, S., & Rochman, D. (2021). Addressing challenges in nuclear data adjustment techniques using integral experiments based upon uranium solution thermal systems. Annals of Nuclear Energy, 163, 108590 (12 pp.). https://doi.org/10.1016/j.anucene.2021.108590
Simulation of breed and burn fuel cycle operation of molten salt reactor in batch-wise refueling mode
Raffuzzi, V., & Krepel, J. (2021). Simulation of breed and burn fuel cycle operation of molten salt reactor in batch-wise refueling mode. 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. 13003 (8 pp.). https://doi.org/10.1051/epjconf/202124713003
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