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Studies of reactor noise response to vibrations of reactor internals and thermal-hydraulic fluctuations in PWRs
Verma, V., Chionis, D., Dokhane, A., & Ferroukhi, H. (2021). Studies of reactor noise response to vibrations of reactor internals and thermal-hydraulic fluctuations in PWRs. Annals of Nuclear Energy, 157, 108212 (19 pp.). https://doi.org/10.1016/j.anucene.2021.108212
Development and verification of a methodology for neutron noise response to fuel assembly vibrations
Chionis, D., Dokhane, A., Belblidia, L., Ferroukhi, H., Girardin, G., & Pautz, A. (2020). Development and verification of a methodology for neutron noise response to fuel assembly vibrations. Annals of Nuclear Energy, 147, 107669 (15 pp.). https://doi.org/10.1016/j.anucene.2020.107669
Impact of various source of covariance information on integral parameters uncertainty during depletion calculations with CASMO-5
Hursin, M., Rochman, D., Vasiliev, A., Ferroukhi, H., & Pautz, A. (2020). Impact of various source of covariance information on integral parameters uncertainty during depletion calculations with CASMO-5. In Proceedings of the PHYSOR 2020 (p. 1172 (10 pp.). Nuclear Energy Group.
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
Modelling and analysis of fuel assembly vibrational modes in PWRs using SIMULATE-3K
Verma, V., Chionis, D., Dokhane, A., & Ferroukhi, H. (2020). Modelling and analysis of fuel assembly vibrational modes in PWRs using SIMULATE-3K. In Proceedings of the PHYSOR 2020 (p. 1270 (8 pp.). Nuclear Energy Group.
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
Analysis of simplified BWR full core with serpent-2/simulate-3 hybrid stochastic/deterministic code
Jo, Y., Hursin, M., Lee, D., Ferroukhi, H., & Pautz, A. (2018). Analysis of simplified BWR full core with serpent-2/simulate-3 hybrid stochastic/deterministic code. Annals of Nuclear Energy, 111, 141-151. https://doi.org/10.1016/j.anucene.2017.08.061
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
Methodology for core analyses with nuclear data uncertainty quantification and application to Swiss PWR operated cycles
Leray, O., Ferroukhi, H., Hursin, M., Vasiliev, A., & Rochman, D. (2017). Methodology for core analyses with nuclear data uncertainty quantification and application to Swiss PWR operated cycles. Annals of Nuclear Energy, 110, 547-559. https://doi.org/10.1016/j.anucene.2017.07.006
Bowing effects on isotopic concentrations for simplified PWR assemblies and full cores
Li, J., Rochman, D., Vasiliev, A., Ferroukhi, H., Herrero, J., Pautz, A., … Janin, D. (2017). Bowing effects on isotopic concentrations for simplified PWR assemblies and full cores. Annals of Nuclear Energy, 110, 1023-1029. https://doi.org/10.1016/j.anucene.2017.08.022
Solution of the BEAVRS benchmark using CASMO-5 / SIMULATE-5 code sequence
Bykov, V., Vasiliev, A., Ferroukhi, H., & Pautz, A. (2016). Solution of the BEAVRS benchmark using CASMO-5 / SIMULATE-5 code sequence. In Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century (pp. 1960-1968). American Nuclear Society.
Nuclear data uncertainty propagation on spent fuel nuclide compositions
Leray, O., Rochman, D., Grimm, P., Ferroukhi, H., Vasiliev, A., Hursin, M., … Pautz, A. (2016). Nuclear data uncertainty propagation on spent fuel nuclide compositions. Annals of Nuclear Energy, 94, 603-611. https://doi.org/10.1016/j.anucene.2016.03.023
Development, verification and test application of a hybrid CASMO-5/SERPENT depletion scheme
Leray, O., Pecchia, M., Vasiliev, A., Ferroukhi, H., Pautz, A., & Perrier, H. (2015). Development, verification and test application of a hybrid CASMO-5/SERPENT depletion scheme. In Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C+SNA+MC 2015) (pp. 1781-1793). American Nuclear Society.
Uncertainty quantification of spent fuel nuclide compositions due to cross sections, decay constants and fission yields
Leray, O., Grimm, P., Hursin, M., Ferroukhi, H., & Pautz, A. (2014). Uncertainty quantification of spent fuel nuclide compositions due to cross sections, decay constants and fission yields (p. 1104088 (13 pp.). Presented at the International conference on physics of reactors (PHYSOR 2014). .
Effects of advanced radial submeshing methods on pin power reconstruction for an EPR core design
Mala, P., Canepa, S., Ferroukhi, H., & Pautz, A. (2014). Effects of advanced radial submeshing methods on pin power reconstruction for an EPR core design (p. 1105669 (12 pp.). Presented at the International conference on physics of reactors (PHYSOR 2014). .
Towards the reanalysis of void coefficients measurements at PROTEUS for High Conversion Light Water Reactor lattices
Hursin, M., Koeberl, O., & Perret, G. (2012). Towards the reanalysis of void coefficients measurements at PROTEUS for High Conversion Light Water Reactor lattices. In Vol. 3. PHYSOR 2012: advances in reactor physics (pp. 2558-2568).