Research interests
• Generation IV Nuclear Reactors
• Nuclear-Thermohydraulic Analysis
• Severe Accidents in Nuclear Reactors
• Development of Computational Platforms for Analysis and Design of Nuclear Reactors
Professor Gilberto Espinosa-Paredes has been a teacher at the Universidad Autónoma Metropolitana (UAM) Campus in Iztapalapa since 1997; he has taught courses on transport phenomena, nuclear and physical reactors, and applied mathematics. He was a special guest at Severe Accident Analysis in Nuclear Power Plants at Science and Technology of Nuclear Installations and has been a member of numerous editorial committees. He is a member of the Mexican Academy of Engineering and the Mexican Academy of Sciences and is a Level III of the National System of Researchers (SNI).
Author of more than 200 publications in nuclear energy and geoenergy, has published six monographic texts, among which the next to be published Fractional-Order Models for Nuclear Reactor Analysis. He has two patent registrations, related measurements of rheological properties between 2 immiscible fluids, and another to estimate the mass flow in nuclear reactors with natural circulation systems. He has collaborated on different technological projects, including the extended power increase of the Green Laguna nuclear power plant and its stability analysis. In 2014, the Best Manuscript Award was awarded at the Hermal Hydraulics Nuclear Congress, Operation and Safety (Nuthos-10).
He is at the forefront of the development of mathematical models for the analysis of thermal fluid in cores of reactors cooled with flows in two phases and liquid metals in the reference framework of the multi-institutional and binational project for the development of the Mexican platform AZTLAN for analysis and design of nuclear reactors.
Tutor of 12 Ph.D. thesis, among which two have received national prizes, two postdoctorate theses, eight master's thesis, and more than 30 degree titles. He is currently the president of the Mexican Network for Nuclear Education and Research. Professor Espinosa-Paredes is recognized as an expert in mathematical models applied to the analysis of nuclear reactors.
*Courses are conducted in spanish
| Num. | Trim. | Course Name | Level |
|---|---|---|---|
| Escalamiento en Fenómenos de Transporte | Posgrado | ||
| Física de Reactores II | Licenciatura | ||
| Investigación Doctoral II | Posgrado | ||
| Investigación Doctoral IX | Posgrado | ||
| Investigación Doctoral V | Posgrado | ||
| Proyecto de Investigación II | Posgrado | ||
| Proyecto de Investigación II | Posgrado | ||
| Proyecto de Investigación II | Posgrado | ||
| Proyecto Terminal I Energía Nuclear | Licenciatura | ||
| Seminario de Investigación II | Posgrado | ||
| Seminario de Investigación II | Posgrado | ||
| Seminario de Investigación II | Posgrado | ||
| Física de Reactores I | Licenciatura | ||
| Investigación Doctoral I | Posgrado | ||
| Investigación Doctoral IV | Posgrado | ||
| Investigación Doctoral VIII | Posgrado | ||
| Métodos de Análisis del Transporte de Neutrones | Posgrado | ||
| Modelado Matemático en Ingeniería en Energía y Medio Ambiente | Posgrado | ||
| Proyecto de Investigación I | Posgrado | ||
| Proyecto de Investigación I | Posgrado | ||
| Proyecto de Investigación I | Posgrado | ||
| Proyecto Terminal II Energía Nuclear | Licenciatura | ||
| Proyecto Terminal II Energías Renovables | Licenciatura | ||
| Seminario de Investigación I | Posgrado | ||
| Seminario de Investigación I | Posgrado | ||
| Seminario de Investigación I | Posgrado | ||
| Termohidráulica de Reactores Nucleares Avanzados | Posgrado | ||
| Termohidráulica de Reactores Nucleares I | Licenciatura | ||
| Física de Reactores II | Licenciatura | ||
| Investigación Doctoral III | Posgrado | ||
| Investigación Doctoral VII | Posgrado | ||
| Métodos de Análisis del Transporte de Neutrones | Posgrado | ||
| Proyecto de Investigación III | Posgrado | ||
| Proyecto de Investigación III | Posgrado | ||
| Proyecto Terminal I Energía Nuclear | Licenciatura | ||
| Proyecto Terminal I Energías Renovables | Licenciatura | ||
| Seminario de Investigación III | Posgrado | ||
| Temas Selectos de Energía Nuclear | Posgrado | ||
| Temas Selectos de Energía Nuclear II | Licenciatura | ||
| Temas Selectos de Energías Renovables | Posgrado | ||
| Escalamiento en Fenómenos de Transporte | Posgrado | ||
| Física de Reactores I | Licenciatura | ||
| Fundamentos de Ingeniería Nuclear | Posgrado | ||
| Investigación Doctoral II | Posgrado | ||
| Investigación Doctoral VI | Posgrado | ||
| Proyecto de Investigación II | Posgrado | ||
| Proyecto de Investigación II | Posgrado | ||
| Proyecto Terminal II Energía Nuclear | Licenciatura | ||
| Seminario de Investigación II | Posgrado | ||
| Seminario de Investigación II | Posgrado | ||
| Temas Selectos de Energía Nuclear I | Licenciatura | ||
| Investigación Doctoral I | Posgrado | ||
| Investigación Doctoral V | Posgrado | ||
| Modelado Matemático en Ingeniería en Energía y Medio Ambiente | Posgrado | ||
| Proyecto de Investigación I | Posgrado | ||
| Proyecto Terminal I Energía Nuclear | Licenciatura | ||
| Seminario de Investigación I | Posgrado | ||
| Termohidráulica de Reactores Nucleares II | Licenciatura | ||
| Física de Reactores II | Licenciatura | ||
| Investigación Doctoral IV | Posgrado |