GOMEZ TORRES, ARMANDO MIGUEL
CIENCIAS TECNOLÓGICAS · Nivel 1
Desde 2005 es Researched en Instituto Nacional de Investigaciones Nucleares Ocoyoacac
| Nombre | ARMANDO MIGUEL GOMEZ TORRES |
|---|---|
| Área | INGENIERÍAS Y DESARROLLO TECNOLÓGICO |
| Campo | CIENCIAS TECNOLÓGICAS |
| Disciplina | TECNOLOGÍA NUCLEAR |
| Especialidad | NEUTRONICA |
| CVU | 387729 |
| Institución | |
|---|---|
| Dependencia | GERENCIA DE CIENCIAS APLICADAS |
| Entidad | MEXICO |
| Nivel | 1 |
| Vigencia | Inicio: 01/01/2023 |
| Fin: 31/12/2027 |
Publicaciones ORCID
- 2026
- Development and implementation of an external neutronic–thermal-hydraulic coupling framework for natural circulation SMR analysis Nuclear Engineering and Design
- 2025
- Simulation and validation of the thermalhydraulic behavior of the QUENCH-04 experiment using TLANESY and ASYST/SCDAPSIM 3.5 codes International Journal of Heat and Mass Transfer
- Validation of the New TLANESY Thermal–Hydraulic Code with Data from the QUENCH-01 Experiment Journal of Nuclear Engineering
- 2024
- Digitalization as an aggregate performance in the energy transition for nuclear industry Nuclear Engineering and Technology
- 2022
- Verification and Validation of the SPL Module of the Deterministic Code AZNHEX through the Neutronics Benchmark of the CEFR Start-Up Tests Journal of Nuclear Engineering
- Upscaling and downscaling the heat transfer process coupled with neutronic reflected core for sodium-cooled fast nuclear reactor International Journal of Heat and Mass Transfer
- Evaluating DualSPHysics performance implemented in the study of heat transfer in multiphase systems with applications in nuclear reactors Computational Particle Mechanics
- Verification of the Parallel Transport Codes Parafish and AZTRAN with the TAKEDA Benchmarks Energies
- Thermomechanical analysis of a lead-cooled fast reactor with a fast-running model Case Studies in Thermal Engineering
- 2021
- Development, verification, and validation of the parallel transport code AZTRAN Progress in Nuclear Energy
