Zobrazeno 1 - 5
of 5
pro vyhledávání: '"Hala K. Selim"'
Autor:
Hala K. Selim, Neama M. El-Sahlamy
Publikováno v:
Kerntechnik. 87:672-682
The pressurizer system of pressurized water reactor (PWR) maintains the reactor coolant system pressure during steady-state operation and limits pressure changes during transients. The in/out surge transients will cause pressure variations and they a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bdaeae3fc5d98515863b27a9b7dd5d0b
https://doi.org/10.1515/kern-2022-0038
https://doi.org/10.1515/kern-2022-0038
Autor:
rania Fhmy, Hala K. Selim
Publikováno v:
SSRN Electronic Journal.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7c3370305fbb59ef25f1336449520c47
https://doi.org/10.2139/ssrn.4225336
https://doi.org/10.2139/ssrn.4225336
Autor:
Hala K. Selim, Neama M. El-Sahlamy
Publikováno v:
Annals of Nuclear Energy. 164:108637
The flow coastdown transient calculation is important for the safety analysis of a nuclear reactor. An accurate transient analysis during coastdown is necessary and important for the design and manufacture of a reactor coolant pump, since only the re
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c24d5b9ffcce77e115e5949c0b1b3438
https://doi.org/10.1016/j.anucene.2021.108637
https://doi.org/10.1016/j.anucene.2021.108637
Publikováno v:
Annals of Nuclear Energy. 109:385-395
One RIA accident, control rod ejection is a design basis accident for LWRs. Hence, it is a postulated event of very low probability, which would have serious consequences if not inherently accounted for in the design of the reactor and the safety sys
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b0375c74c7868165f231dc8034c32709
https://doi.org/10.1016/j.anucene.2017.05.029
https://doi.org/10.1016/j.anucene.2017.05.029
Publikováno v:
Arab Journal of Nuclear Sciences and Applications.
The feasibility of utilizing Thorium-Plutonium Mixed Oxide in the Westinghouse AP1000 Advanced Passive pressurized water reactor is examined under steady-state, beginning of life conditions. Initial core loading of the reactor has three types of UO2
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e6d7c841a0f2457bf515070cba4c4c21
https://doi.org/10.21608/ajnsa.2018.1892.1004
https://doi.org/10.21608/ajnsa.2018.1892.1004