Zobrazeno 1 - 10
of 40
pro vyhledávání: '"A Armenta-Molina"'
Autor:
Alejandra Armenta-Molina, Luis Héctor Hernández-Gómez, Carlos Daniel Pascual-Hernández, Daniel Villaseñor-Chávez, Gilberto Soto-Mendoza, Brayan Leonardo Pérez-Escobar, Tanya Nerina Arreola-Valles, Salatiel Pérez-Montejo
Publikováno v:
Results in Engineering, Vol 24, Iss , Pp 102915- (2024)
The aging evaluation of a typical fuse holder, which is used in a BWR-5 nuclear plant, is discussed in this paper. This evaluation considered the guidelines of the NUREG-1760. A fuse holder, class R, has been considered. It has a wire gauge in the 50
Externí odkaz:
https://doaj.org/article/6d5712daedfb4497a0a638bd55ba9aab
Autor:
Armenta-Molina, Alejandra, Hernández-Gómez, Luis Héctor, Pascual-Hernández, Carlos Daniel, Villaseñor-Chávez, Daniel, Soto-Mendoza, Gilberto, Pérez-Escobar, Brayan Leonardo, Arreola-Valles, Tanya Nerina, Pérez-Montejo, Salatiel
Publikováno v:
In Results in Engineering December 2024 24
Autor:
Juan Alejandro Flores-Campos, Adolfo Perrusquia, Luis Hector Hernandez-Gomez, Noe Gonzalez, Alejandra Armenta-Molina
Publikováno v:
IEEE Access, Vol 9, Pp 65676-65687 (2021)
In this paper, a constant speed control of slider-crank mechanisms for machine tools is proposed. A joint-task space hybrid controller based on a second-order sliding mode control and time-base generator was used to guarantee a constant speed traject
Externí odkaz:
https://doaj.org/article/f4bddd078a3a4378bf699b8870b8b8e4
Autor:
Hernández-Palafox, Edgar, Ruiz-López, Pablo, Hernández Gómez, Luis Héctor, Armenta-Molina, Alejandra, Soto-Mendoza, Gilberto, Alfonso Beltrán-Fernández, Juan, Alberto Arenas-Magos, Luis
Publikováno v:
Nuclear Technology; May2024, Vol. 210 Issue 5, p781-794, 14p
Akademický článek
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Autor:
G. Soto-Mendoza, A. Armenta-Molina, S. Pérez-Montejo, L.H. Hernández-Gómez, P. Ruiz-López, G.M. Urriolagoitia-Calderón, J.A. Beltrán-Fernández
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2021 (2021)
The recirculation system of a BWR-5 has 20 jet pumps. They are submerged in water in the cylindrical annular zone of the reactor. Their main function is the development of a forcing flow through the nuclear core. It increases the power of the reactor
Externí odkaz:
https://doaj.org/article/9f00bcc632184484a741874b35286fea
Publikováno v:
REVMEDUAS. 12:299-308
Objetivo: Evaluar la inhibición del crecimiento de la bacteria Enterococcus faecalis (ATCC® 29212™) en presencia de cementos selladores (CS) utilizados en tratamientos endodónticos mediante experimentación in vitro. --- Materiales y Métodos: S
Autor:
Soto-Mendoza, G.1 (AUTHOR), Armenta-Molina, A.1 (AUTHOR), Pérez-Montejo, S.1 (AUTHOR), Hernández-Gómez, L.H.1 (AUTHOR), Ruiz-López, P.2 (AUTHOR), Urriolagoitia-Calderón, G.M.1 (AUTHOR), Beltrán-Fernández, J.A.1 (AUTHOR)
Publikováno v:
Science & Technology of Nuclear Installations. 3/27/2021, p1-13. 13p.
Autor:
Luis Héctor Hernández-Gómez, Rafael García-Illescas, Lenin Ramos-Cantú, José Javier Moctezuma-Reyes, Alejandra Armenta-Molina, Laura Guadalupe Carbajal-Figueroa, Juan Alfonso Beltrán-Fernández, Tanya Nerina Arreola-Valles
Publikováno v:
Defect and Diffusion Forum. 412:197-206
Thermal fatigue widely takes place in light water reactor (LWR) piping systems. It is an important aging mechanism of a nuclear reactor. Thermal transient effects occur at the startup and shutdown of a nuclear power plant. During the thermal transien
Autor:
Luis Héctor Hernández Gómez, Yunuén López Grijalba, Juan Alfonso Beltrán Fernández, Alejandra Armenta Molina, Pablo Ruiz López, Salatiel Pérez Montejo
Publikováno v:
Journal of Nuclear Science and Technology. 58:1210-1219
Boiling water reactors have internal components manufactured with stainless-steel type 304. Some relevant cracks have been detected through the periodic inspections of their internal components. Re...