Zobrazeno 1 - 10
of 48
pro vyhledávání: '"Javier Ortiz-Villafuerte"'
Autor:
Javier Ortiz-Villafuerte, Andrés Rodríguez-Hernández, Enrique Araiza-Martínez, Luis Fuentes-Márquez, Jorge Viais-Juárez
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2013 (2013)
RELAP/SCDAPSIM Mod 3.4 has been used to simulate a station blackout occurring at a BWR/5 power station. Further, a simplified model of a wet well and dry well has been added to the NSSS model to study the response of the primary containment during th
Externí odkaz:
https://doaj.org/article/18aa522dc46b43839802fd10613370a2
Autor:
Javier Ortiz-Villafuerte, Heriberto Sanchez-Mora, Cesar Queral, Melisa Reyes-Fuentes, Edmundo del-Valle-Gallegos
Publikováno v:
Journal of Nuclear Engineering and Radiation Science.
After the nuclear accident at the Fukushima Daiichi nuclear power plant, hydrogen generation has resurfaced as a key issue, with respect to its quantification in the simulation of severe accidents, because of the potential risk of deflagration or det
Autor:
Heriberto Sánchez-Mora, Javier Ortiz-Villafuerte, Armando M. Gómez-Torres, Cesar Queral, Sergio Quezada-García
Publikováno v:
SSRN Electronic Journal.
Publikováno v:
Nuclear Technology and Radiation Protection, Vol 35, Iss 2, Pp 87-94 (2020)
A computational methodology to estimate the capacity of aerosol particle retention in a filter- ing system based on sand bed is described in this work. This methodology uses a combination of computational fluid dynamics and mechanistic models in the
Autor:
Alejandro Reyes-Garcia Antonio, Javier Ortiz-Villafuerte, Eduardo Sainz-Mejia, Roberto Lopez-Solis Carlos, C Javier Palacios-Hernandez
Publikováno v:
Nuclear Technology and Radiation Protection, Vol 35, Iss 1, Pp 16-23 (2020)
The aim of this project was to determine the capacity of a multi-venturi scrubber filtering system to cope with vented gas mass-flow rate coming from a BWR Mark II primary containment during a long-term station blackout. The multi-venturi filtering s
Autor:
Eduardo Sainz-Mejia, Javier Ortiz-Villafuerte, Armando Miguel Gomez-Torres, Carlos Filio-López, Nancy Astrid Solis-Alcantara, José Vicente Xolocostli-Munguía
Publikováno v:
Nuclear Engineering and Design. 325:57-67
Venting timing and duration are key issues for the development and assessment of severe accident guidelines and mitigation alternatives. In BWRs, venting from wetwell has the advantage of gaining fission product scrubbing. In this study, two strategi
Autor:
Melisa Reyes-Fuentes, Cesar Queral, Julian Duran-Gonzalez, Javier Ortiz-Villafuerte, Armando Miguel Gomez-Torres, Rogelio Castillo-Durán, Edmundo del-Valle-Gallegos
Publikováno v:
Reliability Engineering & System Safety. 209:107441
The AZTLAN Platform project is a Mexican national initiative which aims to have a platform for analysis and design of nuclear reactors. In order to enhance the AZTLAN Platform with Uncertainty and Sensitivity (U&S) capabilities, the AZTUSIA (AZtlan T
Publikováno v:
Nuclear Engineering and Design. 311:1-8
A new detailed geometric model of the whole recirculation loop of a BWR has been developed for the code RELAP. This detailed model includes the 10 jet pumps, 5 risers, manifold, suction and control valves, and the recirculation pump, per recirculatio
Publikováno v:
Nuclear Engineering and Design. 284:67-73
Several methods have been developed for the analysis of reactor power signals during BWR power oscillations. Among them is the Prony's method, its application provides the DR and the frequency of oscillations. In this paper another characteristic of
Publikováno v:
Nuclear Engineering and Design. 241:1469-1477
It is known that Boiling Water Reactors are susceptible to present power oscillations in regions of high power and low coolant flow, in the power-flow operational map. It is possible to fall in one of such instability regions during reactor startup,