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Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo
Alhassan, E., Rochman, D., Sjöstrand, H., Vasiliev, A., Koning, A. J., & Ferroukhi, H. (2020). Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo. Annals of Nuclear Energy, 139, 107239 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107239
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
Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics
Rochman, D., Dokhane, A., Vasiliev, A., Ferroukhi, H., & Hursin, M. (2020). Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics. European Physical Journal Plus, 135, 233 (18 pp.). https://doi.org/10.1140/epjp/s13360-020-00258-2
A comprehensive theoretical assessment of potential 'tramp uranium' isotopic evolution in BWR reactors
Vasiliev, A., Grimm, P., Ferroukhi, H., Pecchia, M., & Ledergerber, G. (2020). A comprehensive theoretical assessment of potential 'tramp uranium' isotopic evolution in BWR reactors. Annals of Nuclear Energy, 144, 107489 (11 pp.). https://doi.org/10.1016/j.anucene.2020.107489
Application of causality analysis on nuclear reactor systems
Chionis, D., Dokhane, A., Ferroukhi, H., & Pautz, A. (2019). Application of causality analysis on nuclear reactor systems. Chaos: An Interdisciplinary Journal of Nonlinear Science, 29(4), 043126 (16 pp.). https://doi.org/10.1063/1.5083905
Spatial localization of perturbation propagation in LWRs using causality and connectivity analysis
Chionis, D., Dokhane, A., Ferroukhi, H., & Pautz, A. (2019). Spatial localization of perturbation propagation in LWRs using causality and connectivity analysis. In International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). LaGrange Park, USA: American Nuclear Society (ANS).
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). La Grange Park, USA: 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
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.
EPR fuel cycle depletion with pin-by-pin code tortin and nodal code SIMULATE5
Mala, P., Pautz, A., & Ferroukhi, H. (2019). EPR fuel cycle depletion with pin-by-pin code tortin and nodal code SIMULATE5. In International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park, USA: American Nuclear Society.
Screening analysis for pressurized thermal shock (PTS) transient scenarios
Mukin, R., Clifford, I., Costa Garrido, O., Mora, D. F., Niffenegger, M., Niceno, B., & Ferroukhi, H. (2019). Screening analysis for pressurized thermal shock (PTS) transient scenarios. In 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park, USA: American Nuclear Society (ANS).
PMSYS: plant management system as a part of Swiss Simulation Platform
Nikitin, K., Clifford, I., & Ferroukhi, H. (2019). PMSYS: plant management system as a part of Swiss Simulation Platform. In 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). LaGrange Park, USA: American Nuclear Society (ANS).
 Assessment of nTRACER and parcs performance for VVER configurations
Papadionysiou, M., Seongchan, K., Hursin, M., Vasiliev, A., Ferroukhi, H., Pautz, A., & Joo, H. G. (2019).  Assessment of nTRACER and parcs performance for VVER configurations. In International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park, USA: American Nuclear Society.
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.
Studies of intra-pin power distributions in operated BWR fuel assemblies using MCNP with a cycle check-up methodology
Pecchia, M., Ferroukhi, H., Vasiliev, A., & Grimm, P. (2019). Studies of intra-pin power distributions in operated BWR fuel assemblies using MCNP with a cycle check-up methodology. Annals of Nuclear Energy, 129, 67-78. https://doi.org/10.1016/j.anucene.2019.01.047
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
Comparison of computational fluid dynamics and subchannel numerical solutions of fuel assemblies characterized by bowing
Puragliesi, R., Mukin, R., Clifford, I., Ferroukhi, H., & Seidl, M. (2019). Comparison of computational fluid dynamics and subchannel numerical solutions of fuel assemblies characterized by bowing. In 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS).
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
Cross-verification of SUHAM-TD and nTracer reactivity insertion transient solutions without materials homogenization approximation using OECD/NEA C5G7-TD benchmark
Vasiliev, A., Canepa, S., Ferroukhi, H., Boyarinov, V. F., Fomichenko, P. A., Joo, H. G., & Ryu, M. (2019). Cross-verification of SUHAM-TD and nTracer reactivity insertion transient solutions without materials homogenization approximation using OECD/NEA C5G7-TD benchmark. Annals of Nuclear Energy, 134, 235-243. https://doi.org/10.1016/j.anucene.2019.06.002
 

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