Publikationen, an denen er mitarbeitet Sebastián Salvador Martorell Alsina (17)

2020

  1. 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

  2. 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

  1. Evaluation of risk impact of completion time changes combining PSA and DSA model insight and human reliability analysis

    Reliability Engineering and System Safety, Vol. 178, pp. 97-107

  2. 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

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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

  6. RELAP5 Simulation of PKL Facility Experiments under Midloop Conditions

    Science and Technology of Nuclear Installations, Vol. 2017

  7. 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

  1. Bootstrapped-ensemble-based Sensitivity Analysis of a trace thermal-hydraulic model based on a limited number of PWR large break loca simulations

    Reliability Engineering and System Safety, Vol. 153, pp. 122-134

  2. Post-test analysis of the ROSA/LSTF and PKL counterpart test

    Nuclear Engineering and Design, Vol. 297, pp. 81-94

2015

  1. 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

  2. LBLOCA Uncertainty analysis using meta models

    International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015

2014

  1. Use of TRACE best estimate code to analyze spent fuel storage pools safety

    Progress in Nuclear Energy, Vol. 77, pp. 224-238

2012

  1. Spent fuel pool analysis using TRACE code

    International Conference on the Physics of Reactors 2012, PHYSOR 2012: Advances in Reactor Physics