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Measurement of the gas velocity in a water-air mixture in CROCUS using neutron noise techniques
Hursin, M., Pakari, O., Perret, G., Frajtag, P., Lamirand, V., Pázsit, I., … Pautz, A. (2020). Measurement of the gas velocity in a water-air mixture in CROCUS using neutron noise techniques. Nuclear Technology. https://doi.org/10.1080/00295450.2019.1701906
Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments
Siefman, D., Hursin, M., Perret, G., & Pautz, A. (2020). Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments. Progress in Nuclear Energy, 121, 103245 (9 pp.). https://doi.org/10.1016/j.pnucene.2020.103245
Measurement of the gas velocity in a water-air mixture in crocus by neutron noise technique
Hursin, M., Pakari, O., Perret, G., Frajtag, P., Lamirand, V., Pázsit, I., … Pautz, A. (2019). Measurement of the gas velocity in a water-air mixture in crocus by neutron noise technique. Presented at the International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). Portland, OR, USA: American Nuclear Society.
Uncertainty quantification of LWR-proteus phase II experiments using CASMO-5
Hursin, M., Park, J., Kim, W., Siefman, D., Perret, G., Vasiliev, A., … Lee, D. (2019). Uncertainty quantification of LWR-proteus phase II experiments using CASMO-5. Presented at the International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). Portland, OR, USA.
An experimental programme optimized with uncertainty propagation: PETALE in the CROCUS reactor
Lamirand, V., Laureau, A., Rochman, D., Perret, G., Gruel, A., Leconte, P., … Pautz, A. (2019). An experimental programme optimized with uncertainty propagation: PETALE in the CROCUS reactor. In O. Serot & A. Chebboubi (Eds.), EPJ web of conferences: Vol. 211. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications. https://doi.org/10.1051/epjconf/201921103003
Uncertainty quantification of LWR-PROTEUS Phase II experiments using CASMO-5
Park, J., Kim, W., Hursin, M., Perret, G., Vasiliev, A., Rochman, D., … Lee, D. (2019). Uncertainty quantification of LWR-PROTEUS Phase II experiments using CASMO-5. Annals of Nuclear Energy, 131, 9-22. https://doi.org/10.1016/j.anucene.2019.03.023
Benchmark Monte Carlo calculations with ENDF/B-VIII.0 and JEFF-3.3 libraries for LWR criticality safety assessments
Pecchia, M., Vasiliev, A., Perret, G., & Ferroukhi, H. (2019). Benchmark Monte Carlo calculations with ENDF/B-VIII.0 and JEFF-3.3 libraries for LWR criticality safety assessments. Presented at the ICNC 2019 - 11th international conference on nuclear criticality safety. Paris, France.
Global sensitivity and registration strategy for temperature profile of reflood experiment simulations
Perret, G., Wicaksono, D., Clifford, I. D., & Ferroukhi, H. (2019). Global sensitivity and registration strategy for temperature profile of reflood experiment simulations. Nuclear Technology, 205(12), 1638-1651. https://doi.org/10.1080/00295450.2019.1591154
First tests of a gamma-blind fast neutron detector prototype based on ZnS and wavelength-shifting fibers
Wolfertz, A., Adams, R., & Perret, G. (2019). First tests of a gamma-blind fast neutron detector prototype based on ZnS and wavelength-shifting fibers. Presented at the ANS annual meeting 2019. The value of nuclear. Minneapolis, USA.
Determination of sobol sensitivity indices for correlated inputs with SHARK-X
Hursin, M., Siefman, D., Perret, G., Rochman, D., Vasiliev, A., & Ferroukhi, H. (2018). Determination of sobol sensitivity indices for correlated inputs with SHARK-X. In Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society.
Testing of a sCVD diamond detection system in the CROCUS reactor
Hursin, M., Weiss, C., Frajtag, P., Lamirand, V., Perret, G., Kavrigin, P., … Griesmayer, E. (2018). Testing of a sCVD diamond detection system in the CROCUS reactor. The European Physical Journal A, 54(5), 82 (11 pp.). https://doi.org/10.1140/epja/i2018-12519-1
Design of separated element reflector experiments in CROCUS: PETALE
Lamirand, V., Perret, G., Radman, S., Siefman, D., Frajtag, P., Hursin, M., … Pautz, A. (2018). Design of separated element reflector experiments in CROCUS: PETALE. In M. H. Sparks, K. R. DePriest, & D. W. Vehar (Eds.), Reactor dosimetry: 16th international symposium. https://doi.org/10.1520/STP160820170090
Intercomparison of neutron noise measurement systems in the CROCUS reactor
Lamirand, V., De Izzarra, G., Krasa, A., Perret, G., Pakari, O., Frajtag, P., … Pautz, A. (2018). Intercomparison of neutron noise measurement systems in the CROCUS reactor. In Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society.
Investigation of spatial effects on neutron noise measurements in the zero power reactor CROCUS
Pakari, O., Lamirand, V., Perret, G., Godat, D., Hursin, M., Frajtag, P., & Pautz, A. (2018). Investigation of spatial effects on neutron noise measurements in the zero power reactor CROCUS. In Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society.
Kinetic parameter measurements in the CROCUS reactor using current mode instrumentation
Pakari, O., Lamirand, V., Perret, G., Frajtag, P., & Pautz, A. (2018). Kinetic parameter measurements in the CROCUS reactor using current mode instrumentation. IEEE Transactions on Nuclear Science, 65(9), 2456-2460. https://doi.org/10.1109/TNS.2018.2831180
Monte Carlo simulation of a scintillation detector for spent fuel characterization in a hot cell
Papadionysiou, M., Perret, G., Zboray, R., Adams, R., & Mosset, J. B. (2018). Monte Carlo simulation of a scintillation detector for spent fuel characterization in a hot cell. Nuclear Engineering and Design, 332, 119-126. https://doi.org/10.1016/j.nucengdes.2018.03.033
Deterministic sampling and Gaussian Process metamodel approach applied to a station black out accident model
Perret, G., Rahman, S., & Wicaksono, D. (2018). Deterministic sampling and Gaussian Process metamodel approach applied to a station black out accident model. Presented at the ANS best estimate plus uncertainty international conference (BEPU 2018). Lucca, Italy.
Nuclear data correlation between different isotopes via integral information
Rochman, D. A., Bauge, E., Vasiliev, A., Ferroukhi, H., & Perret, G. (2018). Nuclear data correlation between different isotopes via integral information. EPJ Nuclear Sciences and Technologies, 4, 7 (10 pp.). https://doi.org/10.1051/epjn/2018006
Analysis of reactivity worths of burnt PWR fuel samples measured in LWR-PROTEUS Phase II using a CASMO-5 reflected-assembly model
Grimm, P., Hursin, M., Perret, G., Siefman, D., & Ferroukhi, H. (2017). Analysis of reactivity worths of burnt PWR fuel samples measured in LWR-PROTEUS Phase II using a CASMO-5 reflected-assembly model. Progress in Nuclear Energy, 101, 280-287. https://doi.org/10.1016/j.pnucene.2017.03.018
Impact of implicit effects on uncertainties and sensitivities of the Doppler coefficient of a LWR pin cell
Hursin, M., Leray, O., Perret, G., Pautz, A., Bostelmann, F., Aures, A., & Zwermann, W. (2017). Impact of implicit effects on uncertainties and sensitivities of the Doppler coefficient of a LWR pin cell. In A. Plompen, F. J. Hambsch, P. Schillebeeckx, W. Mondelaers, J. Heyse, S. Kopecky, … S. Oberstedt (Eds.), EPJ web of conferences: Vol. 146. ND 2016: international conference on nuclear data for science and technology. https://doi.org/10.1051/epjconf/201714609034