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Featured researches published by J. Montero-Mayorga.


Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory | 2014

Development of a PWR-W and an AP1000® Containment Building 3D Model With a CFD Code for Best-Estimate Thermal-Hydraulic Analysis

Gonzalo Jimenez; Rafael Bocanegra; Kevin Fernández; César Queral; J. Montero-Mayorga

The simulation of design basis accidents in a containment building is usually conducted with a lumped parameter model. The codes normally used by Westinghouse Electric Company (WEC) for that license analysis are WGOTHIC or COCO, which are suitable to provide an adequate estimation of the overall peak temperature and pressure of the containment. However, for the detailed study of the thermal-hydraulic behavior in every room and compartment of the containment building, it could be more convenient to model the containment with a more detailed 3D representation of the geometry of the whole building.The main objective of this project is to obtain a standard PWR Westinghouse as well as an AP1000® containment model for a CFD code to analyze the thermal-hydraulic detailed behavior during a design basis accident. In this paper the development and testing of both containment models is presented.Copyright


Annals of Nuclear Energy | 2015

AP1000® Large-Break LOCA BEPU analysis with TRACE code

César Queral; J. Montero-Mayorga; J. Gonzalez-Cadelo; Gonzalo Jimenez


Annals of Nuclear Energy | 2014

Effects of delayed RCP trip during SBLOCA in PWR

J. Montero-Mayorga; César Queral; J. Gonzalez-Cadelo


Annals of Nuclear Energy | 2014

Analysis of cold leg LOCA with failed HPSI by means of integrated safety assessment methodology

J. Gonzalez-Cadelo; César Queral; J. Montero-Mayorga


Annals of Nuclear Energy | 2015

AP1000® SBLOCA simulations with TRACE code

J. Montero-Mayorga; César Queral; J. Gonzalez-Cadelo


Nuclear Engineering and Design | 2014

Effects of RCP trip when recovering HPSI during LOCA in a Westinghouse PWR

J. Montero-Mayorga; César Queral; Julio Rivas-Lewicky; J. Gonzalez-Cadelo


Annals of Nuclear Energy | 2016

Risk reduction due to modification of normal residual heat removal system of AP1000® reactor to meet European Utility Requirements

César Queral; J. Montero-Mayorga


Annals of Nuclear Energy | 2017

Verification of AP1000® low-margin PRA sequences based on best-estimate calculations

César Queral; J. Montero-Mayorga; J. Rivas-Lewicky; M.J. Rebollo


Archive | 2014

International Agreement Report Simulation of LSTF Hot Leg Break (OECD/NEA ROSA-2 Test 1) with TRACE Code: Application to a PWR NPP Model

J. Gonzalez-Cadelo; César Queral; J. Montero-Mayorga; J. C. Martinez Murillo


Ponencias de la 42ª Reunión Anual de la Sociedad Nuclear Española | 42ª Reunión Anual de la Sociedad Nuclear Española | 28-30 septiembre 2016 | Santander (España) | 2016

Estudio de la termo-hidráulica del tanque de agua de recarga (IRWST) en el reactor AP1000® durante un accidente tipo SBLOCA con el código GOTHIC 8.1.

Samanta Estévez; Gonzalo Jiménez Varas; César Queral; J. Montero-Mayorga

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César Queral

Technical University of Madrid

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J. Gonzalez-Cadelo

Technical University of Madrid

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Gonzalo Jimenez

Technical University of Madrid

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J. Rivas-Lewicky

Technical University of Madrid

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Julio Rivas-Lewicky

Technical University of Madrid

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Kevin Fernández

Technical University of Madrid

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M.J. Rebollo

Technical University of Madrid

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Rafael Bocanegra

Technical University of Madrid

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