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Alejandra Armenta Molina
Alejandra Armenta Molina
Instituto Politécnico Nacional
Dirección de correo verificada de esimez.mx
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Constant speed control of slider-crank mechanisms: A joint-task space hybrid control approach
JA Flores-Campos, A Perrusquía, LH Hernández-Gómez, N González, ...
IEEE Access 9, 65676-65687, 2021
152021
Analysis of the leakage-flow-induced vibration of a slip joint in a jet pump of a boiling water reactor
JC Castro, EH Palafox, IAA Sánchez, LH Hernández-Gómez, ...
Defect and Diffusion Forum 390, 23-31, 2019
42019
Evaluation of the structural integrity of a BWR core shroud with non-regular locations of circumferential cracks. Part I fracture analysis
P Ruiz López, LHH Gómez, YL Grijalba, A Armenta Molina, ...
Journal of Nuclear Science and Technology 58 (11), 1210-1219, 2021
22021
Cross flow analysis over the jet pumps of a BWR-5 reactor
G Soto-Mendoza, A Armenta-Molina, S Pérez-Montejo, ...
Science and Technology of Nuclear Installations 2021, 1-13, 2021
12021
Review of electromagnetic compatibility on digital systems of nuclear power plants
IA Alarcón-Sánchez, R Linares-y-Miranda, LH Hernández-Gómez, ...
Engineering Design Applications III: Structures, Materials and Processes …, 2020
12020
Environmental Fatigue Analysis of the Feedwater Piping System of a BWR-5
LG Carbajal-Figueroa, S Pérez-Montejo, A Armenta-Molina, ...
Engineering Design Applications III: Structures, Materials and Processes, 71-80, 2020
12020
Structural Vibrations in a Building of a Nuclear Power Plant Caused by an Underground Blasting
A Armenta-Molina, A Villanueva-García, G Soto-Mendoza, ...
Engineering Design Applications III: Structures, Materials and Processes, 81-90, 2020
12020
Impact Analysis of a Commercial Airplane Over a Nuclear Spent Fuel Dry Storage Cask
E Hernández-Palafox, P Ruiz-López, LH Hernández Gómez, ...
Nuclear Technology, 1-14, 2023
2023
Buckling Analysis of an Origami-Inspired Structure with the Finite Element Method
JJ Moctezuma-Reyes, LH Hernández-Gómez, A Armenta-Molina, ...
Engineering Design Applications V: Structures, Materials and Processes, 295-303, 2023
2023
Accumulated Damage of the Main Steam Nozzle of a BWR-5
TN Arreola-Valles, LH Hernández-Gómez, A Armenta-Molina, ...
Engineering Design Applications V: Structures, Materials and Processes, 305-315, 2023
2023
Evaluation of the environmental fatigue at a long radius elbow of a piping system under transient thermo mechanical stresses
L Ramos-Cantú, LH Hernández-Gómez, R García-Illescas, ...
Defect and Diffusion Forum 412, 197-206, 2021
2021
Evaluation of the Environmental Fatigue at a Long Radius Elbow of a Piping System under Transient Thermo Mechanical Stresses
R García-Illescas, TN Arreola-Valles, JJ Moctezuma-Reyes, ...
Transfer Phenomena in Fluid and Heat Flows XIII, 197, 2021
2021
Numerical analysis of the BWR-5 beltline region containing a crack postulated for an extended period of operation
SP Montejo, PR López, GS Mendoza, AA Molina, AV García, LHH Gómez
Procedia Structural Integrity 17, 123-130, 2019
2019
Evaluation of the structural integrity of a boiling water reactor skirt under stationary and transient loading conditions
YL Grijalba, LHH Gómez, PR López, GMU Calderón, GS Mendoza, ...
Engineering Design Applications, 495-505, 2019
2019
Análisis de envejecimiento de los pernos de cierre de la tapa de una vasija de un reactor nuclear tipo BWR
G Soto-Mendoza, J Cruz-Castro, A Armenta-Molina, ...
Científica 21 (1), 35-41, 2017
2017
Constant Speed Control of Slider-Crank Mechanisms: A Joint-Task Space Hybrid Control Approach
NOÉ GONZÁLEZ, A ARMENTA-MOLINA
El sistema no puede realizar la operación en estos momentos. Inténtalo de nuevo más tarde.
Artículos 1–16