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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<sub>3</sub>Si<sub>2</sub>/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).
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). .
Full core LOCA analysis for BWR/6 - methodology and first results
Cozzo, C., Epiney, A., Canepa, S., Ferroukhi, H., Zerkak, O., Khvostov, G., … Gorzel, A. (2016). Full core LOCA analysis for BWR/6 - methodology and first results. In Top Fuel 2016. LWR fuels with enhanced safety and performance (pp. 1135-1144). American Nuclear Society.