Zobrazeno 1 - 7
of 7
pro vyhledávání: '"Rowayda F. Mahmoud"'
Publikováno v:
Kerntechnik. 87:615-624
Democratic Republic of Congo (DRC) has a TRIGA mark II research reactor called TRICO II, its design power is 1.00 MW. The reactor was in extended shutdown state since November 2004. The DRC government has decided to resume its operation using the las
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3619413463bafdb5ad3e9b4ec17a9f14
https://doi.org/10.1515/kern-2022-0016
https://doi.org/10.1515/kern-2022-0016
Publikováno v:
Arab Journal of Nuclear Sciences and Applications. :1-8
Nuclear characterization of the spent nuclear fuel in a reactor core is essential, especially in case of severe accidents. The radionuclide inventory and its activity can assist in the management of spent fuel handling, transport, or reprocessing. In
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::77a6b18fc114e4e609158f719b797772
https://doi.org/10.21608/ajnsa.2021.40762.1397
https://doi.org/10.21608/ajnsa.2021.40762.1397
Autor:
Sahelemariam Tafesse Kitawa, Rowayda F. Mahmoud Abou Alo, Said A. Agamy, Mohsen Abdou Abou Mandour
Publikováno v:
2022 4th International Youth Conference on Radio Electronics, Electrical and Power Engineering (REEPE).
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::653e3d54a13a661f0ac4a3a7decb75e7
https://doi.org/10.1109/reepe53907.2022.9731436
https://doi.org/10.1109/reepe53907.2022.9731436
Publikováno v:
Journal of Physics: Conference Series. 1439:012003
High fuel burn-up and long cycle length are the main objectives for economic and reliable operation of Advanced Nuclear Power Reactors. The selected cladding material to stand for high burn-up and long cycle length is HANA-4 alloy. AP1000 core was de
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d387104c0f1b200c2717f3bc340e9b4f
https://doi.org/10.1088/1742-6596/1439/1/012003
https://doi.org/10.1088/1742-6596/1439/1/012003
Publikováno v:
Nuclear Engineering and Design. 280:628-633
The criticality safety calculations were performed for a proposed design of a wet spent fuel storage pool. This pool will be used for the storage of spent fuel discharged from a typical pressurized water reactor (PWR). The mathematical model based on
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d6fde7517b9a53c1bf814c0ce6b43796
https://doi.org/10.1016/j.nucengdes.2014.09.001
https://doi.org/10.1016/j.nucengdes.2014.09.001
Publikováno v:
Journal of Physics: Conference Series; 2020, Vol. 1439 Issue 1, p1-1, 1p
Publikováno v:
Kerntechnik; Oct2022, Vol. 87 Issue 5, p615-624, 10p