Active Filters

  • (-) PSI Groups = 4804 Advanced Nuclear Systems
Search Results 1 - 20 of 31
Select Page
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
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
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
Closed U-Pu and Th-U cycle in sixteen selected reactors: comparison of major equilibrium features
Krepel, J., & Losa, E. (2019). Closed U-Pu and Th-U cycle in sixteen selected reactors: comparison of major equilibrium features. Annals of Nuclear Energy, 128, 341-357. https://doi.org/10.1016/j.anucene.2019.01.013
Simulations of advanced reactor cores in research light water reactor LR-0
Losa, E., Košťál, M., Jánský, B., Novák, E., Rypar, V., Chvála, O., & Křepel, J. (2019). Simulations of advanced reactor cores in research light water reactor LR-0. Nuclear Engineering and Design, 342, 205-209. https://doi.org/10.1016/j.nucengdes.2018.12.007
Enhancements along with application of the Asymptotic Progressing nuclear data Incremental Adjustment (APIA) methodology by individual assimilations of fast reactor data
Pelloni, S., & Rochman, D. (2019). Enhancements along with application of the Asymptotic Progressing nuclear data Incremental Adjustment (APIA) methodology by individual assimilations of fast reactor data. Annals of Nuclear Energy, 129, 79-89. https://doi.org/10.1016/j.anucene.2019.01.057
Analysis of hypothetical Unprotected Loss Of Flow in Superphénix start-up core: sensitivity to modeling details
Ponomarev, A., & Mikityuk, K. (2019). Analysis of hypothetical Unprotected Loss Of Flow in Superphénix start-up core: sensitivity to modeling details. The proceedings of the international conference on nuclear engineering (ICONE): Vol. 2019.27. . Presented at the 27th international conference on nuclear engineering (ICONE-27). sine loco: The Japan Society of Mechanical Engineers.
A coarse-mesh methodology for modelling of single-phase thermal-hydraulics of ESFR innovative assembly design
Radman, S., Fiorina, C., Mikityuk, K., & Pautz, A. (2019). A coarse-mesh methodology for modelling of single-phase thermal-hydraulics of ESFR innovative assembly design. Nuclear Engineering and Design, 355, 110291 (17 pp.). https://doi.org/10.1016/j.nucengdes.2019.110291
Correlation <em>ν̅</em> <sub><em>p</em><em> </em></sub>– <em>σ </em>for U-Pu in the thermal and resonance neutron range via integral information
Rochman, D., Vasiliev, A., Ferroukhi, H., Pelloni, S., Bauge, E., & Koning, A. (2019). Correlation ν̅ p σ for U-Pu in the thermal and resonance neutron range via integral information. European Physical Journal Plus, 134, 453 (12 pp.). https://doi.org/10.1140/epjp/i2019-12875-7
Analysis of major group structures used for nuclear reactor simulations
Di Filippo, M., Krepel, J., Mikityuk, K., & Prasser, H. M. (2018). Analysis of major group structures used for nuclear reactor simulations. In Proceedings of the 26th international conference on nuclear engineering (ICONE26). Student paper competition. https://doi.org/10.1115/ICONE26-81445
Creation of an OpenFOAM fuel performance class based on FRED and integration into the GeN-Foam multi-physics code
Fiorina, C., Pautz, A., & Mikityuk, K. (2018). Creation of an OpenFOAM fuel performance class based on FRED and integration into the GeN-Foam multi-physics code. In Proceedings of the 26th international conference on nuclear engineering (ICONE26). Nuclear fuel and material, reactor physics, and transport theory. https://doi.org/10.1115/ICONE26-81574
Proposal of new safety measures for European sodium fast reactor to be evaluated in framework of Horizon-2020 ESFR-SMART project
Guidez, J., Rineiski, A., Prêle, G., Girardi, E., Bodi, J., & Mikityuk, K. (2018). Proposal of new safety measures for European sodium fast reactor to be evaluated in framework of Horizon-2020 ESFR-SMART project. In Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018. American Nuclear Society.
Chugging boiling in low-void SFR core: new phenomenology of unprotected loss of flow
Mambelli, S., Mikityuk, K., & Panadero, A. L. (2018). Chugging boiling in low-void SFR core: new phenomenology of unprotected loss of flow. In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vienna: International Atomic Energy Agency.
New safety measures proposed for European Sodium Fast Reactor in Horizon-2020 ESFR-SMART project
Mikityuk, K. (2018). New safety measures proposed for European Sodium Fast Reactor in Horizon-2020 ESFR-SMART project. Presented at the GIF Symposium. Paris, France.
Use of CAD models in ESFR-SMART project
Mikityuk, K., & Ponomarev, A. (2018). Use of CAD models in ESFR-SMART project. Presented at the GIF Symposium. Paris, France.