J. F.
Villanueva
Publications by the researcher in collaboration with J. F. Villanueva (13)
2020
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Parametric and non-parametric methods for estimating multidimensional tolerance regions associated to safety margins
Proceedings of the 29th European Safety and Reliability Conference, ESREL 2019
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Uncertainty analysis of a loss of cooling and loss of coolant accident in a spent fuel pool using TRACE
Progress in Nuclear Energy, Vol. 124
2018
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Uncertainty analysis of a large break loss of coolant accident in a pressurized water reactor using non-parametric methods
Reliability Engineering and System Safety, Vol. 174, pp. 19-28
2017
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A comparison between traditional BEPU and extended-BEPU approaches for deterministic safety analysis on nuclear power plants
Risk, Reliability and Safety: Innovating Theory and Practice - Proceedings of the 26th European Safety and Reliability Conference, ESREL 2016
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A comparison of performance between order statistics and metamodeling in safety margins uncertainty quantification
Safety and Reliability - Theory and Applications - Proceedings of the 27th European Safety and Reliability Conference, ESREL 2017
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An approach to merge PSA-based premises and BEPU method in order to develop the EBEPU methodology
PSAM 2016 - 13th International Conference on Probabilistic Safety Assessment and Management
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An extended BEPU approach integrating probabilistic assumptions on the availability of safety systems in deterministic safety analyses
Reliability Engineering and System Safety, Vol. 167, pp. 474-483
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RELAP5 Simulation of PKL Facility Experiments under Midloop Conditions
Science and Technology of Nuclear Installations, Vol. 2017
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Uncertainty analysis of PKL SBLOCA G7.1 test simulation using TRACE with Wilks and GAM surrogate methods
Nuclear Engineering and Design, Vol. 319, pp. 61-72
2016
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Post-test analysis of the ROSA/LSTF and PKL counterpart test
Nuclear Engineering and Design, Vol. 297, pp. 81-94
2015
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Comparison of some approaches for the estimation of tolerance limits in the context of lbloca uncertainty analysis
International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
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LBLOCA Uncertainty analysis using meta models
International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
2012
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Spent fuel pool analysis using TRACE code
International Conference on the Physics of Reactors 2012, PHYSOR 2012: Advances in Reactor Physics