Zobrazeno 1 - 10
of 44
pro vyhledávání: '"Pedro Carajilescov"'
Autor:
Duvan A. Castellanos-Gonzalez, João Manoel Losada Moreira, José Rubens Maiorino, Pedro Carajilescov
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2018 (2018)
This article presents the validation of the Code for Thermal-hydraulic Evaluation of Nuclear Reactors with Plate Type Fuels (COTENP), a subchannel code which performs steady-state thermal-hydraulic analysis of nuclear reactors with plate type fuel as
Externí odkaz:
https://doaj.org/article/e4fc079640b04c32bb75ad98a60fcdee
Autor:
Pedro Carajilescov, Duvan A. Castellanos-Gonzalez, João Manoel Losada Moreira, J. R. Maiorino
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2018 (2018)
This article presents the validation of the Code for Thermal-hydraulic Evaluation of Nuclear Reactors with Plate Type Fuels (COTENP), a subchannel code which performs steady-state thermal-hydraulic analysis of nuclear reactors with plate type fuel as
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6b82135192356b2ea82d8f882de7b993
https://doi.org/10.1155/2018/9874196
https://doi.org/10.1155/2018/9874196
Publikováno v:
Energy Policy. 87:334-346
The power generation sector in Brazil is usually considered to have a high level of sustainability because of its large share of hydropower, about 70%. The annual growth rate of the Brazilian power sector is about 4%/year with a growing capacity addi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d1bd28c0e8feb6a9371292a2fe631295
https://doi.org/10.1016/j.enpol.2015.09.021
https://doi.org/10.1016/j.enpol.2015.09.021
Publikováno v:
Energy Policy. 55:531-542
The construction time of PWRs is studied considering published data about nuclear power plants in the world. For the 268 PWRs in operation in 2010, the mode of the construction time distribution is around 5–6 years, and 80% of the plants were built
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::97d2a136dfc9af178258a3e7907c083d
https://doi.org/10.1016/j.enpol.2012.12.044
https://doi.org/10.1016/j.enpol.2012.12.044
Publikováno v:
Procceedings of the 16th Brazilian Congress of Thermal Sciences and Engineering.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b1568de32fcccee0b7cc128ecd6e6c75
https://doi.org/10.26678/abcm.encit2016.cit2016-0142
https://doi.org/10.26678/abcm.encit2016.cit2016-0142
Publikováno v:
Journal of the Brazilian Society of Mechanical Sciences. 22:291-302
An experimental investigation is performed in a turbulent flow in a seven wire-wrapped rod bundle, mounted in an open air facility. Static pressure distributions are measured on central and peripheral rods. By using a Preston tube, the wall shear str
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c576fb20c40647226d12c8b4405b25a9
https://doi.org/10.1590/s0100-73862000000200012
https://doi.org/10.1590/s0100-73862000000200012
Publikováno v:
Journal of the Brazilian Society of Mechanical Sciences, Volume: 22, Issue: 4, Pages: 613-622, Published: 2000
In nuclear reactors, the occurrence of critical heat flux leads to fuel rod overheating with clad fusion and radioactive products leakage. To predict the effects of such phenomenon, experiments are performed using electrically heated rods to simulate
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5adb036bff057faf83d0911414dae6c5
https://doi.org/10.1590/s0100-73862000000400010
https://doi.org/10.1590/s0100-73862000000400010
Publikováno v:
Journal of the Brazilian Society of Mechanical Sciences, Volume: 22, Issue: 4, Pages: 599-612, Published: 2000
Fuel elements of PWR type nuclear reactors consist of rod bundles, arranged in a square array, and held by spacer grids. The coolant flows, mainly, axially along the rods. Although such elements are laterally open, experiments are performed in closed
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::0ebb657ac75806d03fbeb9e1fa01ee74
https://doi.org/10.1590/s0100-73862000000400009
https://doi.org/10.1590/s0100-73862000000400009
Publikováno v:
Journal of the Brazilian Society of Mechanical Sciences. 21:589-599
The fuel element of LMFBR consists of a bundle of rods wrapped with an helical wire as spacer, surrounded by an hexagonal duct. In the present work, a semi-empirical model is developed to calculate bundle average and subchannel based friction factors
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5dcd1ba27ea04137add53c2654a03b90
https://doi.org/10.1590/s0100-73861999000400003
https://doi.org/10.1590/s0100-73861999000400003
Autor:
Pedro Carajilescov, Neil E. Todreas
Publikováno v:
Nuclear Engineering and Design. 30:3-19
In the thermal design of nuclear reactor cores, specified design limits (temperatures and linear power rating) should not be exceeded by the operating values of certain elements (coolant, clad and fuel). However, a certain number of channels or fuel
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4c57f190eb783d4ac1e2357c8c153a4c
https://doi.org/10.1016/0029-5493(74)90146-0
https://doi.org/10.1016/0029-5493(74)90146-0