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Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark
Skorek, T., de Crécy, A., Kovtonyuk, A., Petruzzi, A., Mendizábal, R., de Alfonso, E., … Pautz, A. (2019). Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark. Nuclear Engineering and Design, 354, 110199 (23 pp.). https://doi.org/10.1016/j.nucengdes.2019.110199
Modeling and analysis of selected organization for economic cooperation and development PKL-3 station blackout experiments using TRACE
Mukin, R., Clifford, I., Zerkak, O., & Ferroukhi, H. (2018). Modeling and analysis of selected organization for economic cooperation and development PKL-3 station blackout experiments using TRACE. Nuclear Engineering and Technology, 50(3), 356-367. https://doi.org/10.1016/j.net.2017.12.005
Deterministic sampling for propagating epistemic and aleatory uncertainty in dynamic event tree analysis
Rahman, S., Karanki, D. R., Epiney, A., Wicaksono, D., Zerkak, O., & Dang, V. N. (2018). Deterministic sampling for propagating epistemic and aleatory uncertainty in dynamic event tree analysis. Reliability Engineering and System Safety, 175, 62-78. https://doi.org/10.1016/j.ress.2018.03.009
Analysis of Oskarshamn-2 stability event using TRACE/SIMULATE-3K and comparison to TRACE/PARCS and SIMULATE-3K stand-alone
Dokhane, A., Judd, J., Gajev, I., Zerkak, O., Ferroukhi, H., & Kozlowski, T. (2017). Analysis of Oskarshamn-2 stability event using TRACE/SIMULATE-3K and comparison to TRACE/PARCS and SIMULATE-3K stand-alone. Annals of Nuclear Energy, 102, 190-199. https://doi.org/10.1016/j.anucene.2016.12.015
Development and validation of a TRACE/PARCS core model of Leibstadt Kernkraftwerk cycle 19
Hursin, M., Bogetic, S., Dohkane, A., Canepa, S., Zerkak, O., Ferroukhi, H., & Pautz, A. (2017). Development and validation of a TRACE/PARCS core model of Leibstadt Kernkraftwerk cycle 19. Annals of Nuclear Energy, 101, 559-575. https://doi.org/10.1016/j.anucene.2016.11.001
Epistemic and aleatory uncertainties in integrated deterministic and probabilistic safety assessment: tradeoff between accuracy and accident simulations
Karanki, D. R., Rahman, S., Dang, V. N., & Zerkak, O. (2017). Epistemic and aleatory uncertainties in integrated deterministic and probabilistic safety assessment: tradeoff between accuracy and accident simulations. Reliability Engineering and System Safety, 162, 91-102. https://doi.org/10.1016/j.ress.2017.01.015
Testing the NURESIM platform on a PWR main steam line break benchmark
Kliem, S., Kozmenkov, Y., Hadek, J., Perin, Y., Fouquet, F., Bernard, F., … Mala, P. (2017). Testing the NURESIM platform on a PWR main steam line break benchmark. Nuclear Engineering and Design, 321, 8-25. https://doi.org/10.1016/j.nucengdes.2017.05.028
System code validation series based on a consistent plant nodalisation of the ROSA/LSTF integral test facility using TRACE v5.0 Patch 4
Clifford, I., Zerkak, O., Pautz, A., Yao, H., & Freixa, J. (2016). System code validation series based on a consistent plant nodalisation of the ROSA/LSTF integral test facility using TRACE v5.0 Patch 4 (p. N11A0424 (15 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). .
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.
Towards a consolidated approach for the assessment of evaluation models of nuclear power reactors
Epiney, A., Canepa, S., Zerkak, O., & Ferroukhi, H. (2016). Towards a consolidated approach for the assessment of evaluation models of nuclear power reactors. Nuclear Technology, 196(2), 223-237. https://doi.org/10.13182/NT16-47
Modeling and analysis of selected OECD PKL3 Station-Blackout experiments using TRACE
Mukin, R., Zerkak, O., & Pautz, A. (2016). Modeling and analysis of selected OECD PKL3 Station-Blackout experiments using TRACE (p. N11A0310 (16 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). .
Influence of URANS turbulence models on in-vessel flow mixing during cold leg accumulator injection
Puragliesi, R., Zerkak, O., & Pautz, A. (2016). Influence of URANS turbulence models on in-vessel flow mixing during cold leg accumulator injection (p. N11P0292 (15 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). .
Steady-state CFD simulations of an EPRTM reactor pressure vessel: a validation study based on the JULIETTE experiments
Puragliesi, R., Zhou, L., Zerkak, O., & Pautz, A. (2016). Steady-state CFD simulations of an EPRTM reactor pressure vessel: a validation study based on the JULIETTE experiments. Nuclear Engineering and Design, 300, 41-56. https://doi.org/10.1016/j.nucengdes.2015.12.025
Evaluation of deterministic sampling for uncertainty quantification in a probabilistic accident analysis model
Rahman, S., Karanki, D. R., Wicaksono, D., Zerkak, O., & Dang, V. N. (2016). Evaluation of deterministic sampling for uncertainty quantification in a probabilistic accident analysis model (p. N11P0291 (15 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). .
Bayesian calibration of thermal-hydraulics model with time-dependent output
Wicaksono, D., Zerkak, O., & Pautz, A. (2016). Bayesian calibration of thermal-hydraulics model with time-dependent output (p. N11P0491 (14 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). .
Global sensitivity analysis of transient code output applied to a reflood experiment model using the TRACE code
Wicaksono, D., Zerkak, O., & Pautz, A. (2016). Global sensitivity analysis of transient code output applied to a reflood experiment model using the TRACE code. Nuclear Science and Engineering, 184(3), 400-429. https://doi.org/10.13182/NSE16-37
Computational fluid dynamics analysis of the fluid flow and heat transfer in the core bypass region of a PWR
Clifford, I., Vasiliev, A., Zerkak, O., Ferroukhi, H., & Pautz, A. (2015). Computational fluid dynamics analysis of the fluid flow and heat transfer in the core bypass region of a PWR. In 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16) (pp. 7806-7819). American Nuclear Society.
TRACE/SIMULATE-3K analysis of the NEA/OECD Oskarshamn-2 stability benchmark
Dokhane, A., Zerkak, O., Ferroukhi, H., Gajev, I., Judd, J., & Kozlowski, T. (2015). TRACE/SIMULATE-3K analysis of the NEA/OECD Oskarshamn-2 stability benchmark. In 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16) (pp. 4757-4770). American Nuclear Society.
Towards a consolidated approach for the validation of plant system codes and models: case study for a BWR fast depressurisation event
Epiney, A., Canepa, S., Zerkak, O., & Ferroukhi, H. (2015). Towards a consolidated approach for the validation of plant system codes and models: case study for a BWR fast depressurisation event. In 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16) (pp. 2157-2170). American Nuclear Society.
Modelling guidelines for core exit temperature simulations with system codes
Freixa, J., Martínez-Quiroga, V., Zerkak, O., & Reventós, F. (2015). Modelling guidelines for core exit temperature simulations with system codes. Nuclear Engineering and Design, 286, 116-129. https://doi.org/10.1016/j.nucengdes.2015.02.003