Zobrazeno 1 - 10
of 23
pro vyhledávání: '"Abdelfatah Abdelmaksoud"'
Publikováno v:
International Journal of Thermofluids, Vol 20, Iss , Pp 100411- (2023)
A computational fluid dynamics (CFD) study is conducted for silicon ingot irradiation facility in a typical material testing reactor (MTR). The ingots are placed inside the irradiation device in staggered and in-line bundles. The configurations are v
Externí odkaz:
https://doaj.org/article/ad408e0c7aee494cbbcafec7edc61884
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 1, Pp 54-59 (2019)
The main objective of nuclear reactor safety is to maintain the nuclear fuel in a thermally safe condition with enough safety margins during normal operation and anticipated operational occurrences. In this research, core flow bypass is studied under
Externí odkaz:
https://doaj.org/article/527d0b84f1844d96bbde38b1ef770e1b
Publikováno v:
Nuclear Technology. 209:857-871
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0f89a61a679011b824b957a47ea045d6
https://doi.org/10.1080/00295450.2022.2158667
https://doi.org/10.1080/00295450.2022.2158667
Publikováno v:
International Journal of Thermofluids, Vol 7, Iss , Pp 100020- (2020)
Heat transfer deterioration (HTD) phenomena in supercritical water is one of the most thermal hydraulic critical issues for supercritical reactors. The onset of heat transfer deterioration and bouncy effect have been studied in details, however limit
Externí odkaz:
https://doaj.org/article/01f7dc6180aa478a841cbbf49c83d375
Publikováno v:
International Journal of Thermofluids, Vol 1, Iss , Pp 100013- (2020)
In this work, the closure flow values effect on the penetration depth of radioactive water inside the core chimney of a typical MTR reactor is studied numerically using commercial CFD software ANSYS FLUENT. The closure flow values within the chimney
Externí odkaz:
https://doaj.org/article/80c042001be24561a04a565b257e6615
In the present study, heat transfer characteristics of natural convection of air through 7x7 horizontal bank of tubes of 1cm diameter are studied numerically using Ansys-Fluent CFD code. Both the inline and staggered arrangements are considered. The
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::37a88ae64180a78154520939bc438008
Publikováno v:
Nuclear Technology. 208:1471-1483
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::00c5da088de0d9f489f8fa95728e5ae3
https://doi.org/10.1080/00295450.2022.2035644
https://doi.org/10.1080/00295450.2022.2035644
Publikováno v:
Journal of Mechanical, Civil and Industrial Engineering. 3:13-27
Heat exchangers are devices whose primary responsibility is to transfer heat, typically from one fluid to another. In such applications, the heat exchangers can be parallel flow, crossflow, or counter flow. An essential part of any heat exchanger ana
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5cde5e1b5e15e033b950505956320194
https://doi.org/10.32996/jmcie.2022.3.1.3
https://doi.org/10.32996/jmcie.2022.3.1.3
Publikováno v:
Kerntechnik. 87:48-58
The purpose of this work was to perform a thermal–hydraulic numerical analysis of a nanofluid as the coolant in a typical MTR (material testing reactor) core. Numerical simulation was carried out for turbulent flow of water based nanofluid of diffe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::03f3b485c522a34da79f1f2b8287e7b6
https://doi.org/10.1515/kern-2021-1020
https://doi.org/10.1515/kern-2021-1020
Publikováno v:
Kerntechnik. 84:59-67
The main objective for reactor engineering and inherent safety features is to keep the nuclear fuel in a thermally safe condition with enough safety margins during all operational states (normal-abnormal and accidental states). In this work, an accid
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6abb77e39dd138a6beb8b9a71a58e1f4
https://doi.org/10.3139/124.110874
https://doi.org/10.3139/124.110874