Zobrazeno 1 - 7
of 7
pro vyhledávání: '"Nikolas Lymberis Scuro"'
Autor:
Nikolas Lymberis Scuro, Pedro Ernesto Umbehaun, Edvaldo Angelo, Gabriel Angelo, Delvonei Alves de Andrade
Publikováno v:
Brazilian Journal of Radiation Sciences, Vol 7, Iss 2B (2019)
After a loss of coolant accident (LOCA), fuel rods may balloon. The swelling can partially block the flow channel, affecting the coolability during reflood phase. In order to analyze the influence of blockage length, using a radial blockage of 90%, v
Externí odkaz:
https://doaj.org/article/4c691f28300b41ce965daf7c7aa76c06
Autor:
L. O. Freire, M. O. Menezes, R. R. Pacheco, Delvonei Alves de Andrade, M. S. Rocha, Nikolas Lymberis Scuro
Publikováno v:
World Journal of Nuclear Science and Technology. :96-111
Correlations for the extension of a water vapor jet injected in a liquid pool were historically proposed considering the mass flux (kg/m2/s) as a constant. The results were satisfactory, however adjusting the values by linear regression. Although, it
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cb30b6f01390582725a1d9ed7cddeab0
https://doi.org/10.4236/wjnst.2019.92007
https://doi.org/10.4236/wjnst.2019.92007
Autor:
Michelangelo Durazzo, Marco Aurélio de Mesquita, Elita Fontenele Urano de Carvalho, Miguel Luiz Miotto Negro, Nikolas Lymberis Scuro, Delvonei Alves de Andrade
Publikováno v:
Brazilian Journal of Radiation Sciences. 9
The demand for nuclear fuel for research reactors is increasing worldwide. However, some nuclear fuel factories have small production volumes. There is a gap in the literature regarding how to expand capacity of those facilities in a safe and reliabl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::14ad671934f390580243f28beb02902c
https://doi.org/10.15392/bjrs.v9i1.1588
https://doi.org/10.15392/bjrs.v9i1.1588
Publikováno v:
Nuclear Engineering and Design. 328:321-332
A three-dimensional numerical study on steady state was designed for a safety relief valve using several openings and inlet pressures. The ANSYS-CFX® commercial code was used as a CFD tool to obtain several properties using dry saturated steam revis
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::734a03781e8fb2f8f22fa5c460d41568
https://doi.org/10.1016/j.nucengdes.2018.01.024
https://doi.org/10.1016/j.nucengdes.2018.01.024
Autor:
Antonio Teixeira e Silva, Delvonei Alves de Andrade, Mitsuo Yamaguchi, Pedro E. Umbehaun, José Antonio Batista Souza, Walmir M. Torres, Nikolas Lymberis Scuro, Roberto Navarro de Mesquita
Publikováno v:
World Journal of Nuclear Science and Technology. :54-69
This paper presents the sequence of activities to improve the thermal hydraulic analysis of the IEA-R1 research reactor to operate in safe conditions after power upgrade from 2 to 5 MW and core size reduction from 30 to 24 fuel assemblies. A realisti
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a8bbbc7b3402381cfa9dcd25f4dafb01
https://doi.org/10.4236/wjnst.2018.82006
https://doi.org/10.4236/wjnst.2018.82006
Autor:
Nikolas Lymberis Scuro
Publikováno v:
Repositório Institucional do IPEN
Instituto de Pesquisas Energéticas e Nucleares (IPEN)
instacron:IPEN
Biblioteca Digital de Teses e Dissertações da USP
Universidade de São Paulo (USP)
instacron:USP
Instituto de Pesquisas Energéticas e Nucleares (IPEN)
instacron:IPEN
Biblioteca Digital de Teses e Dissertações da USP
Universidade de São Paulo (USP)
instacron:USP
As simulações numéricas de acidentes em reatores nucleares de pesquisa necessitam de constante aprimoramento, originando metodologias validadas, o que permite aproximar os cálculos numéricos a um comportamento físico. O trabalho proposto consis
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::97e388c33e996db68649fb83a5ac4cf5
https://doi.org/10.11606/d.85.2019.tde-25102019-154117
https://doi.org/10.11606/d.85.2019.tde-25102019-154117
Autor:
Delvonei Alves de Andrade, Nikolas Lymberis Scuro, Gabriel Angelo, Edvaldo Angelo, Pedro E. Umbehaun
Publikováno v:
Brazilian Journal of Radiation Sciences. 7
After a loss of coolant accident (LOCA), fuel rods may balloon. The swelling can partially block the flow channel, affecting the coolability during reflood phase. In order to analyze the influence of blockage length, using a radial blockage of 90%, v
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ba320cda1f6ae871248f330b8ac89716
https://doi.org/10.15392/bjrs.v7i2b.437
https://doi.org/10.15392/bjrs.v7i2b.437