Zobrazeno 1 - 10
of 16
pro vyhledávání: '"Pablo Ruiz-López"'
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...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d2cbcf2f993167f1620e2d27af60997d
https://doi.org/10.1080/00223131.2021.1931519
https://doi.org/10.1080/00223131.2021.1931519
Autor:
Pablo Ruiz López, Yunuén López Grijalba, Luis Héctor Hernández Gómez, Israel Sanchez, Juan Cruz Castro, Juan Alfonso Beltrán Fernández
Publikováno v:
Defect and Diffusion Forum. 399:105-114
Flow-induced vibrations occur in some of the internal components of a nuclear reactor. When specific conditions are present, these vibrations may result in excessive deformations or fatigue that can generate mechanical damage. Several boiling water r
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::771b51292ee91ebbf1b627c3f94cae97
https://doi.org/10.4028/www.scientific.net/ddf.399.105
https://doi.org/10.4028/www.scientific.net/ddf.399.105
Autor:
Pablo Ruiz López, Luis Héctor Hernández Gómez, Juan Cruz Castro, Gilberto Soto Mendoza, Yunuén López Grijalba, Edgar Hernández Palafox
Publikováno v:
Procedia Structural Integrity. 17:115-122
This paper presents the evaluation of the Cumulative Usage Factor (CUF) of the structural girders of an overhead traveling bridge crane. This type of crane is located inside the reactor building of a BWR Nuclear Power Plant. It is important to mentio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::694b28b65abd8a8362bb9b679d815a40
https://doi.org/10.1016/j.prostr.2019.08.016
https://doi.org/10.1016/j.prostr.2019.08.016
Autor:
Salatiel Pérez Montejo, Abraham Villanueva García, Alejandra Armenta Molina, Gilberto Soto Mendoza, Pablo Ruiz López, Luis Héctor Hernández Gómez
Publikováno v:
Procedia Structural Integrity. 17:123-130
In the case of a BWR-5, the wall of the reactor vessel located adjacent to the core is named beltline and it is subjected to neutron embrittlement, lowering the fracture toughness and increasing the yield strength of the material. Cracks can be devel
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::84eee903314959e832584ab693a15a4b
https://doi.org/10.1016/j.prostr.2019.08.017
https://doi.org/10.1016/j.prostr.2019.08.017
Autor:
Irving Alvarez-Loya, Pablo Ruiz-López, Juan Alfonso Beltrán-Fernández, Yunuén López-Grijalba, Luis Héctor Hernández-Gómez, Laura Guadalupe Carbajal-Figueroa
Publikováno v:
Defect and Diffusion Forum. 390:151-160
This paper shows the methodology used for the evaluation of the structural integrity of a boiling water reactor (BWR-5). This evaluation is relevant, because this vessel is the coolant pressure boundary for cooling the nuclear core. In the case of th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e7a4ae53dc11e3d09f69e33f32594d3f
https://doi.org/10.4028/www.scientific.net/ddf.390.151
https://doi.org/10.4028/www.scientific.net/ddf.390.151
Autor:
J. Cruz Castro, E. Hernández Palafox, Pablo Ruiz-López, I.A. Alarcón Sánchez, Luis Héctor Hernández-Gómez, A. Armenta Molina
Publikováno v:
Defect and Diffusion Forum. 390:23-31
The purpose of this analysis is to evaluate the structural integrity of the jet pump assembly of a BWR during the performance of its operational and safety functions. The natural frequencies and vibration modes of the jet pump assembly immersed in wa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a6ef1ee71e55f50217ba600a262ec206
https://doi.org/10.4028/www.scientific.net/ddf.390.23
https://doi.org/10.4028/www.scientific.net/ddf.390.23
Autor:
Gilberto Soto-Mendoza, Pablo Ruiz-López, Alejandra Armenta-Molina, Juan Alfonso Beltrán-Fernández, Salatiel Pérez-Montejo, Guillermo Urriolagoitia-Calderón, Luis Héctor Hernández-Gómez
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://explore.openaire.eu/search/publication?articleId=doi_dedup___::33c4d130d1b231f68bab128386f329a1
Autor:
Salatiel Pérez-Montejo, Gilberto Soto-Mendoza, Juan Alfonso Beltrán-Fernández, Luis Héctor Hernández-Gómez, Abraham Villanueva-García, Pablo Ruiz-López, Alejandra Armenta-Molina, Guillermo Urriolagoitia-Calderón
Publikováno v:
Advanced Structured Materials ISBN: 9783030390617
In this paper, a methodology has been proposed to obtain the response spectrum of a nuclear building caused by underground detonations. For the problem at hand, a reinforced concrete building containing a boiling water reactor was postulated. It was
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ecdca91aafd3027c0e8b1054e24d8420
https://doi.org/10.1007/978-3-030-39062-4_8
https://doi.org/10.1007/978-3-030-39062-4_8
Autor:
Gilberto Soto-Mendoza, Luis Héctor Hernández-Gómez, Salatiel Pérez-Montejo, Laura Guadalupe Carbajal-Figueroa, Pablo Ruiz-López, Alejandra Armenta-Molina, Juan Alfonso Beltrán-Fernández
Publikováno v:
Advanced Structured Materials ISBN: 9783030390617
The fatigue analyses are usually carried out with experimental data obtained in dry conditions. Nevertheless, a wet environment significantly affects the fatigue life of the elements exposed to these conditions. In this paper, the structural integrit
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9e6268ef35726c05557df3fa4c6a322f
https://doi.org/10.1007/978-3-030-39062-4_7
https://doi.org/10.1007/978-3-030-39062-4_7
Autor:
Brayan Leonardo Pérez-Escobar, Salatiel Pérez-Montejo, Pablo Ruiz-López, Luis Héctor Hernández-Gómez, Juan Alfonso Beltrán-Fernández, Krisselby Ivonne Jiménez-Santiago, Juan Alejandro Flores-Campos, Guillermo Urriolagoitia-Calderón
Publikováno v:
Defect and Diffusion Forum. 370:162-170
In this paper, the Cumulative Usage Factor (CUF) of a High Pressure Core Cooling System (HPCS) reactor nozzle of a Boiling Water Reactor was calculated. This fatigue damage has been caused by the sudden injection of cold water into the reactor vessel
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c6abe2e7fa96f58c3b81544254fb10e8
https://doi.org/10.4028/www.scientific.net/ddf.370.162
https://doi.org/10.4028/www.scientific.net/ddf.370.162