Active Filters

  • (-) PSI Authors = Cozzo, Cedric
  • (-) Keywords ≠ coordination environment
Search Results 1 - 20 of 32
Select Page
P2M simulation exercise on past fuel melting irradiation experiments
D’Ambrosi, V., Sercombe, J., Bejaoui, S., Chaieb, A., Baurens, B., Largenton, R., … Peltonen, J. (2024). P2M simulation exercise on past fuel melting irradiation experiments. Nuclear Technology, 210(2), 189-2015. https://doi.org/10.1080/00295450.2023.2194270
Development and testing of the hydrogen behavior tool for Falcon - HYPE
Konarski, P., Cozzo, C., Khvostov, G., & Ferroukhi, H. (2024). Development and testing of the hydrogen behavior tool for Falcon - HYPE. Nuclear Engineering and Technology, 56(2), 728-744. https://doi.org/10.1016/j.net.2023.11.012
FEM heat transfer modelling with tomography-based SiC<sub>f</sub>/SiC unit cell
Cavaliere, A., Marone, F., Cozzo, C., Buchanan, K., Lorrette, C., & Pouchon, M. A. (2023). FEM heat transfer modelling with tomography-based SiCf/SiC unit cell. High Temperatures-High Pressures, 52(2), 95-110. https://doi.org/10.32908/hthp.v52.1281
Modeling of hydrogen behavior in liner claddings
Konarski, P., Cozzo, C., Khvostov, G., & Ferroukhi, H. (2023). Modeling of hydrogen behavior in liner claddings. Journal of Nuclear Materials, 573, 154125 (11 pp.). https://doi.org/10.1016/j.jnucmat.2022.154125
Appraisal of the NRC H-uptake calculation for Swiss boiling water reactors
Cozzo, C., Khvostov, G., Clifford, I., & Ferroukhi, H. (2022). Appraisal of the NRC H-uptake calculation for Swiss boiling water reactors. Nuclear Engineering and Design, 391, 111731 (5 pp.). https://doi.org/10.1016/j.nucengdes.2022.111731
P2M simulation exercise on past fuel melting irradiation experiments: main outcomes on fuel melting assessment in PWR fuel
D'Ambrosi, V., Sercombe, J., Beajoui, S., Chaieb, A., Baurens, B., Largenton, R., … Peltonen, J. (2022). P2M simulation exercise on past fuel melting irradiation experiments: main outcomes on fuel melting assessment in PWR fuel. In TopFuel 2022 light water reactor fuel performance conference (pp. 344-353). https://doi.org/10.13182/TopFuel22-38827
EUROSAFE: fostering the sharing of nuclear expertise
Cozzo, C., Allagbe, C., Alonso, J. R., Ben Ouaghrem, K., Cizelj, L., Degueldre, D., … Yesypenko, Y. (2021). EUROSAFE: fostering the sharing of nuclear expertise. In C. Vázquez-Rodriguez, A. Jiménez Carrascosa, S. Estevez Albuja, & L. F. Duran Vinuesa (Eds.), Book of Proceedings. European nuclear young generation forum 2021 (pp. 623-626). European Nuclear Young Generation Forum.
Quantifying the benefits of the reduced oxidation kinetics in chromium-coated cladding: a parametric study
Cozzo, C., Lind, T., Bertsch, J., Nichenko, S., & Girardin, G. (2021). Quantifying the benefits of the reduced oxidation kinetics in chromium-coated cladding: a parametric study. In C. Vázquez-Rodriguez, A. Jiménez Carrascosa, S. Estevez Albuja, & L. F. Duran Vinuesa (Eds.), Book of Proceedings. European nuclear young generation forum 2021 (pp. 245-248). European Nuclear Young Generation Forum.
Extension of Falcon's modelling capabilities to dry storage: development of a new model for hydrogen behavior in duplex claddings
Konarski, P., Cozzo, C., Khostov, G., & Ferroukhi, H. (2021). Extension of Falcon's modelling capabilities to dry storage: development of a new model for hydrogen behavior in duplex claddings. In TopFuel2021 (p. (10 pp.). European Nuclear Society.
Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling
Konarski, P., Cozzo, C., Khvostov, G., & Ferroukhi, H. (2021). Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling. Journal of Nuclear Materials, 555, 153138 (26 pp.). https://doi.org/10.1016/j.jnucmat.2021.153138
Dry storage modeling activities at PSI: implementation and testing of a creep model for dry storage
Konarski, P., Cozzo, C., Khvostov, G., & Ferroukhi, H. (2020). Dry storage modeling activities at PSI: implementation and testing of a creep model for dry storage. Kerntechnik, 85(6), 419-425. https://doi.org/10.3139/124.200072
First assessments of the dynamic gap conductance model in TRACE
Clifford, I., Cozzo, C., & Ferroukhi, H. (2019). First assessments of the dynamic gap conductance model in TRACE. In 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18) (pp. 4624-4636). American Nuclear Society (ANS).
Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs
Clifford, I., Pecchia, M., Mukin, R., Cozzo, C., Ferroukhi, H., & Gorzel, A. (2019). Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs. Annals of Nuclear Energy, 130, 440-451. https://doi.org/10.1016/j.anucene.2019.03.017
Modeling of the U&lt;sub&gt;3&lt;/sub&gt;Si&lt;sub&gt;2&lt;/sub&gt;/SiC fuel system behavior for a RIA scenario
Cozzo, C., Ngayam-Happy, R., Chen, J. C., Pecchia, M., & Girardin, G. (2019). Modeling of the U3Si2/SiC fuel system behavior for a RIA scenario. In Global/top fuel 2019 (pp. 643-647). American Nuclear Society (ANS).
ATF developments in FALCON V1 at PSI
Cozzo, C., & Khvostov, G. (2018). ATF developments in FALCON V1 at PSI. In Topfuel 2018. Part 4 (p. A0112 (9 pp.). European Nuclear Society.
SiC cladding thermal conductivity requirements for normal operation and LOCA conditions
Cozzo, C., & Rahman, S. (2018). SiC cladding thermal conductivity requirements for normal operation and LOCA conditions. Progress in Nuclear Energy, 106, 278-283. https://doi.org/10.1016/j.pnucene.2018.03.016
Fuel thermo-mechanical simulations with uncertainty quantification and sensitivity analysis of the OECD/NEA RIA code benchmark using FALCON and URANIE
Ngayam-Happy, R., Cozzo, C., Khvostov, G., Krack, M., & Ferroukhi, H. (2018). Fuel thermo-mechanical simulations with uncertainty quantification and sensitivity analysis of the OECD/NEA RIA code benchmark using FALCON and URANIE. In ANS international conference on best-estimate plus uncertainties methods (BEPU-2018) (pp. 2018-124 (11 pp.). American Nuclear Society.
New insights in the fuel grain subdivision during in-plant irradiation up to high burn-up
Chollet, M., Cozzo, C., Bertsch, J., Martin, M., Grolimund, D., & Samson, V. A. (2017). New insights in the fuel grain subdivision during in-plant irradiation up to high burn-up (p. (9 pp.). Presented at the Water reactor fuel performance meeting 2017 (WRFPM 2017). .
Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels
Chollet, M., Krsjak, V., Cozzo, C., & Bertsch, J. (2017). Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels. EPJ Nuclear Sciences and Technologies, 3, 3 (5 pp.). https://doi.org/10.1051/epjn/2016040
SiC cladding behavior: experiments and modelling at PSI
Cozzo, C., Bertsch, J., Fave, L., Rahman, S., Dokhane, A., Krack, M., … Pytel, M. (2017). SiC cladding behavior: experiments and modelling at PSI (p. (10 pp.). Presented at the Water reactor fuel performance meeting 2017 (WRFPM 2017). .