Study of the TN24p dry cask cooling by heat pipes

Annals Of Nuclear Energy - 1/11/2023

10.1016/j.anucene.2023.109981 Ver en origen

• ISSN 03064549

• iMarina

Comparative thermo-hydraulic study of different nuclear spent fuel cask designs using CFD codes

Annals Of Nuclear Energy - 1/11/2023

10.1016/j.anucene.2023.110006 Ver en origen

• ISSN 03064549

• iMarina

Assessment of the depressurization and mixing effects of two spray systems in the PANDA facility, part I – Experimental results

Nuclear Engineering And Design - 1/10/2023

10.1016/j.nucengdes.2023.112453 Ver en origen

• ISSN 00295493

• iMarina

Modelling fuel assembly flow nozzles in a spent nuclear fuel dry cask using CFD codes

Annals Of Nuclear Energy - 1/1/2023

10.1016/j.anucene.2022.109540 Ver en origen

• ISSN 03064549

• iMarina

Assessment of the depressurisation and mixing effects of two spray systems in the PANDA facility, part II – Simulations using GOTHIC8.3(QA)

Nuclear Engineering And Design - 1/1/2023

10.1016/j.nucengdes.2022.112120 Ver en origen

• ISSN 00295493

• iMarina

Towards an optimized management of accidents

Epj Nuclear Sciences & Technologies - 21/12/2022

10.1051/epjn/2022019 Ver en origen

• ISSN 24919292

• iMarina

PARUPM: A simulation code for passive auto-catalytic recombiners

Epj Nuclear Sciences & Technologies - 22/11/2022

10.1051/epjn/2022046 Ver en origen

• ISSN 24919292

• iMarina

Nuclear spent fuel cask full scope simulation using coupled Computational Fluid Dynamics models

Progress In Nuclear Energy - 1/1/2022

10.1016/j.pnucene.2022.104459 Ver en origen

• ISSN 01491970

• iMarina

Integral modelling for nuclear spent fuel Dry storage systems using computational fluid Dynamics

Annals Of Nuclear Energy - 1/1/2022

10.1016/j.anucene.2021.108851 Ver en origen

• ISSN 03064549

• iMarina

AP1000 Passive Containment Cooling System study under LBLOCA conditions using the GOTHIC code

Nuclear Engineering And Design - 1/1/2021

10.1016/j.nucengdes.2021.111442 Ver en origen

• ISSN 00295493

• iMarina

Scaling down of PWR nuclear power plant secondary side conditions for SIRIO experimental facility and verification using system thermal-hydraulic codes. S. Larriba, R. Krpan, G. Jiménez, E. Redondo, C. Queral, I. Kljenak. 31st International Conference Nuclear Energy for New Europe. September 12-15 Portoroz Eslovenia.

12/9/2022

• iMarina

Bringing Nuclear Technology to the Society during the Coronavirus Lockdown

Nestet-2021 Conference - 15/11/2021

• iMarina

Evaluation model of a spent fuel dry cask storage system with TRACE v5p5

24/9/2019

• iMarina

Thermal study of several spent fuel cask distributions in a repository using CFD codes

International Conference On Nuclear Engineering, Proceedings, Icone - 18/5/2019

• iMarina

Containment instrumentation survival under a SA with harsh pressure and temperature conditions

Sammi-2020: Oecd/Nea Specialist Workshop On Advanced Measurement Method And Instrumentation For Enhancing Severe Accident Management In An Npp Addressing Emergency, Stabilization And Long-Term Recovery Phase (p. 1-11) - 12/5/2019

• iMarina

Updating of Almaraz NPP containment models with GOTHIC 8.2 QA

44ª Reunión Anual De La Sociedad Nuclear Española (p. 1-8) - 26/9/2018

• iMarina

Desarrollo de un modelo 3D de contención de la Central Nuclear de Trillo mediante un proceso de modelización optimizado

44ª Reunión Anual De La Sociedad Nuclear Española (p. 1-8) - 26/9/2018

• iMarina

Mesh independence studies for containment models with Porous CFD codes

44ª Reunión Anual De La Sociedad Nuclear Española (p. 1-8) - 26/9/2018

• iMarina

Hipótesis alternativas en el análisis del accidente de la unidad 2 de Fukushima Dai-Ichi con MELCOR 2.1

44ª Reunión Anual De La Sociedad Nuclear Española (p. 1-8) - 26/9/2018

• iMarina

Estudio de un contenedor de combustible gastado mediante una simulación de geometría reducida empleando el código ANSYS CFX

44ª Reunión Anual De La Sociedad Nuclear Española (p. 1-8) - 26/9/2018

• iMarina

Metodología para el desarrollo de modelos de contenedores de combustible nuclear gastado mediante el código Ansys CFX

20/5/2022

• iMarina

Methodology for spent fuel dry cask thermal-hydraulics analysis for long term storage

1/1/2021

• iMarina

Análisis de las estrategias de venteo y la evolución de la concentración de hidrógeno durante un SBO en una contención BWR Mark III con el código GOTHIC 8.3

1/1/2021

• iMarina

Development of an AP1000 3D full containment model using an innovative approach

1/1/2020

• iMarina

Towards a BEPU Methodology for Containment Safety Analyses

1/1/2019

• iMarina

Analysis and improvement of hydrogen mitigation strategies during a severe accident in nuclear containments

1/1/2017

• iMarina

A proposed methodology for passive autocatalytic recombiners sizing and location in LWR containments

1/1/2016

• iMarina