Zobrazeno 1 - 10
of 25
pro vyhledávání: '"Gaiane Sabundjian"'
Publikováno v:
Brazilian Journal of Radiation Sciences. 9
The aim of this paper is evaluated the consequences to ANGRA 2 nuclear power reactor and to identify the flow regimes, the heat transfer modes, and the correlations used by RELAP5/MOD3.2.gama code in ANGRA 2 during the Small-Break Loss-of-Coolant Acc
Publikováno v:
Nuclear Power Plants-The Processes from the Cradle to the Grave
Through a severe accident at nuclear power plant Angra 2, the whole body dose effective of the individuals members of the public located in the Emergency Planning Zones (EPZs) will be calculated, and later, the protective actions in these EPZs will b
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c51f2a85bfd7767f3ee019410b7c64ae
http://www.intechopen.com/articles/show/title/calculation-of-the-dose-for-public-individuals-due-to-a-severe-accident-at-the-angra-2-nuclear-plant
http://www.intechopen.com/articles/show/title/calculation-of-the-dose-for-public-individuals-due-to-a-severe-accident-at-the-angra-2-nuclear-plant
Publikováno v:
Revista Internacional de Ciências; v. 10, n. 1 (2020): Revista Internacional de Ciências; 3-21
Revista Internacional de Ciência
Universidade do Estado do Rio de Janeiro (UERJ)
instacron:UERJ
Revista Internacional de Ciência
Universidade do Estado do Rio de Janeiro (UERJ)
instacron:UERJ
O objetivo deste trabalho foi simular e avaliar com o código RELAP5 o acidente base de projeto de perda de refrigerante primário devido a uma ruptura média na linha de surto do pressurizador da usina nuclear Angra 2. Este acidente foi uma quebra d
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b0eb22fc50dd4c19a932d4649a160f84
https://www.e-publicacoes.uerj.br/index.php/ric/article/view/44530
https://www.e-publicacoes.uerj.br/index.php/ric/article/view/44530
Autor:
Walmir M. Torres, Paulo H. F. Masotti, Pedro E. Umbehaun, Gaiane Sabundjian, Leonardo F. Castro, Roberto Navarro de Mesquita, Delvonei Alves de Andrade, Marcelo da S. Rocha
Publikováno v:
Nuclear Engineering and Design. 335:161-171
Many of the recent nuclear power plant projects use natural circulation as heat removal mechanism. The accuracy of heat transfer parameters estimation has been improved through models that require precise prediction of two-phase flow pattern transiti
Publikováno v:
Energy and Power Engineering. 10:1-9
Among the several methods used to solve the Navier-Stokes equations Hierarchical Expansion Method has demonstrated satisfactory results. This work aimed to apply the expansion of the variables in hierarchical functions for the solution of the Navier-
Publikováno v:
Annals of Nuclear Energy. 105:249-258
The heat transfer mechanism of natural convection has been extensively studied as a passive heat removal system of new nuclear power plants. Considering this aspect, the main objective of this study is to present an assessment of RELAP5 linear-equati
Publikováno v:
Energy and Power Engineering. :86-99
This work presents a new application for the Hierarchical Function Expansion Method for the solution of the Navier-Stokes equations for compressible fluids in two dimensions and in high velocity. This method is based on the finite elements method usi
Autor:
Walmir M. Torres, Pedro E. Umbehaun, Gaiane Sabundjian, Eduardo Maprelian, José Roberto Berretta, Antonio Belchior Junior
Publikováno v:
Nuclear Engineering and Design. 363:110610
The safety of nuclear facilities has been a growing global concern, mainly after the Fukushima nuclear accident. Studies on nuclear research reactor accidents such as the Loss of Coolant Accident (LOCA), many times considered a design basis accident,
Publikováno v:
Revista Cincia, Tecnologia & Ambiente. 4:45-55
Devido a ocorrencia de acidentes nucleares, organizacoes reguladoras nucleares mundiais incluiram a analise de acidentes considerados como acidentes base de projeto – Perda de Refrigerane Primario grande ou pequenas-rupturas (Losso of Coolant Accid