| Analysis of primary bleed and feed strategies for selected SBLOCA sequences in a German Konvoi PWR using ASTEC V2. 0 I Gómez-García-Toraño, VH Sánchez-Espinoza, R Stieglitz, C Queral Annals of Nuclear Energy 110, 818-832, 2017 | 16 | 2017 |
| Investigation of SAM measures during selected MBLOCA sequences along with Station Blackout in a generic Konvoi PWR using ASTECV2. 0 I Gómez-García-Toraño, VHS Espinoza, R Stieglitz Annals of Nuclear Energy 105, 226-239, 2017 | 15 | 2017 |
| Further Development of Severe Accident Management Strategies for a German PWR Konvoi Plant Based on the European Severe Accident Code ASTEC I Gómez García-Toraño Karlsruher Institut für Technologie (KIT), 2017 | 14 | 2017 |
| Assessment of primary and secondary bleed and feed procedures during a Station Blackout in a German Konvoi PWR using ASTECV2. 0 I Gómez-García-Toraño, VH Sánchez-Espinoza, R Stieglitz, C Queral, ... Annals of Nuclear Energy 113, 476-492, 2018 | 12 | 2018 |
| Validation of ASTECV2. 1 based on the QUENCH-08 experiment I Gómez-García-Toraño, VH Sánchez-Espinoza, R Stieglitz, J Stuckert, ... Nuclear Engineering and Design 314, 29-43, 2017 | 11 | 2017 |
| Validation of selected CESAR friction models of the ASTECV21 code based on Moby Dick experiments I Gómez-García-Toraño, L Laborde Journal of Nuclear Engineering and Radiation Science 5 (2), 020908, 2019 | 9 | 2019 |
| Overview of the CESAR thermalhydraulic module of ASTEC V2. 1 and selected validation studies I Gómez-García-Toraño, L Laborde, JA Zambaux IYNC2018, 11-17, 2018 | 7 | 2018 |
| Modelling reflooding of intact core geometries in ASTEC V2. 1: Improvements and validation on PERICLES experiments I Gómez-García-Toraño, L Laborde Nuclear Engineering and Design 378, 111157, 2021 | 5 | 2021 |
| Reflooding of degraded cores in ASTEC V2. 1: modelling and validation on PEARL experiments I Gómez-García-Toraño, L Laborde, F Fichot, H Mutelle Nuclear Engineering and Design 393, 111768, 2022 | 4 | 2022 |
| Analysis of pwr severe accident sequences including mitigative measures to prevent or delay the failure of safety barriers with the severe accident code ASTEC V Sanchez Espinoza, I Gómez-García-Toraño Topical Issues in Nuclear Installation Safety: Safety Demonstration of …, 2018 | | 2018 |
| Development of a model of a NSSS of the PWR reactor with thermo-hydraulic code GOTHIC; Desarrollo de un modelo del NSSS de un reactor PWR con el codigo termo-hidraulico GOTHIC I Gomez Garcia-Torano, G Jimenez | | 2013 |
