Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Duvan A. Castellanos-Gonzalez"'
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
Publikováno v:
Brazilian Journal of Radiation Sciences, Vol 9, Iss 2B (2021)
The cooling of a nuclear reactor depends on a suitable fluid flow pattern among its fuel elements aiming the removal of heat produced in the fuel. In case of light water reactors, an excess of heat drives the fluid to change its phase from liquid to
Externí odkaz:
https://doaj.org/article/39a15dd79ced479cbe42e3015afdb137
Publikováno v:
Brazilian Journal of Radiation Sciences. 9
The cooling of a nuclear reactor depends on a suitable fluid flow pattern among its fuel elements aiming the removal of heat produced in the fuel. In case of light water reactors, an excess of heat drives the fluid to change its phase from liquid to
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7237a5a97dc335aa1a9ca1a14833f60e
https://doi.org/10.15392/bjrs.v9i2b.1403
https://doi.org/10.15392/bjrs.v9i2b.1403
Publikováno v:
Nuclear Engineering and Design. 390:111711
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6f349ff69dfcc6ba9b7f8fc371439301
https://doi.org/10.1016/j.nucengdes.2022.111711
https://doi.org/10.1016/j.nucengdes.2022.111711
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
Autor:
J. R. Maiorino, Duvan A. Castellanos-Gonzalez, João Manoel Losada Moreira, Deiglys Borges Monteiro
Publikováno v:
Nuclear Engineering and Design. 369:110827
The study of two-phase flow behavior is a very important requirement in nuclear reactor systems, due to it can appear during normal operating conditions in a BWR or fast and slow transients for both PWR and BWR reactors. This work presents the evalua
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::949d20c66dc481b5b616fab268c96b95
https://doi.org/10.1016/j.nucengdes.2020.110827
https://doi.org/10.1016/j.nucengdes.2020.110827