Zobrazeno 1 - 10
of 30
pro vyhledávání: '"N. Ashoub"'
Publikováno v:
Kerntechnik. 80:454-464
This paper illustrates the neutronic and thermal hydraulic models that were implemented in the nuclear research reactor simulator based on LabVIEW. It also describes the system and transient analysis of the simulator that takes into consideration the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6decfb48a1dedcbff8a509cf2c63fb5e
https://doi.org/10.3139/124.110535
https://doi.org/10.3139/124.110535
Publikováno v:
Kerntechnik. 79:518-527
This paper introduces the development of a research reactor educational simulator based on LabVIEW that allows the training of operators and studying different accident scenarios and the effects of operational parameters on the reactor behavior. Usin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::967fe96637c18a17fc2105a5d61e4a1a
https://doi.org/10.3139/124.110446
https://doi.org/10.3139/124.110446
Autor:
N. Ashoub, H. G. Saleh
Publikováno v:
Kerntechnik. 70:138-141
Safety analysis of research reactors include a determination of control rod worth and kinetic parameters upon which the dynamic performance of the reactor depends. The core control of the ET-RR-2 reactor is accomplished through six Ag-In-Cd alloy-abs
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::67cd93d22dac20aa1759d353ce041452
https://doi.org/10.3139/124.100236
https://doi.org/10.3139/124.100236
Publikováno v:
Kerntechnik. 67:111-115
The second Egyptian research reactor ET-RR-2, is a pool type reactor. A sudden loss of pool water would leave the core region uncovered. The reactor core is surrounded by chimney chambers with water isolated from the pool water. This accident would l
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e1422d1554737b30f25515e340e5bec9
https://doi.org/10.1515/kern-2002-0046
https://doi.org/10.1515/kern-2002-0046
Autor:
N. Ashoub, H. G. Saleh
Publikováno v:
Kerntechnik. 66:273-278
The ET-RR-1 research reactor has been operated at 2 MW since 1961 using EK-10 fuel elements with 10% enriched uranium. The reactor has been used for nuclear applied research and isotope production. In order to upgrade the reactor power to a reasonabl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::452edd3b2b78488a3187f569f52c4cbf
https://doi.org/10.1515/kern-2001-0106
https://doi.org/10.1515/kern-2001-0106
Publikováno v:
Nuclear Engineering and Design. 208:245-254
In the present work, power up-grading study is performed, for the first Egyptian Research Reactor (ET-RR-1), using the present fuel basket with 4×4 fuel rods, (17.5 mm pitch), and a proposed fuel basket with 5×5 fuel rods, (14.0 mm pitch), without
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f8905cddfea7ca4c4e0b3e6e8998ed8b
https://doi.org/10.1016/s0029-5493(01)00359-4
https://doi.org/10.1016/s0029-5493(01)00359-4
Autor:
N. Ashoub
Publikováno v:
Nuclear Engineering and Design. 208:255-263
The second Egyptian Research Reactor ET-RR-2 is a multipurpose research reactor. It is an open pool type, with nominal power of 22 MW water-cooled. The reactor pool is designed to accommodate two fuel test loops mainly 500 and 20 KW loop in the react
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::985a24ea7741923fee04a104549fe6bf
https://doi.org/10.1016/s0029-5493(01)00360-0
https://doi.org/10.1016/s0029-5493(01)00360-0
Publikováno v:
Kerntechnik. 66:177-181
The start up physics studies SPS of the Second Egyptian Research Reactor is presented in this work. The SPS consists of the approach to criticality, the power and flux distribution of the first critical core, criticality, power and flux distribution
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::53b93861c47062a5170b3234af73567f
https://doi.org/10.1515/kern-2001-0077
https://doi.org/10.1515/kern-2001-0077
Publikováno v:
Annals of Nuclear Energy. 27:841-854
The ET-RR-2 safety analysis evaluation effort included the assessment of the reactor core nuclear design parameters. The present work complements the previous effort of neutronic calculations using NCNSRC computer code packages. This paper is the fir
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5b092512107270fe6a34bc0e9339fe3e
https://doi.org/10.1016/s0306-4549(99)00091-2
https://doi.org/10.1016/s0306-4549(99)00091-2
Autor:
N. Ashoub, H.G. Saleh
Publikováno v:
Annals of Nuclear Energy. 27:553-561
The present fuel element of the ET-RR1 research reactor has a 1.75 cm lattice pitch. The neutronic studies were proved that, this lattice pitch is over moderated and not the suitable one from the fuel economic point of view. Two fuel lattice pitches
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::38d73fab9d6de8f339430197669b81c3
https://doi.org/10.1016/s0306-4549(99)00073-0
https://doi.org/10.1016/s0306-4549(99)00073-0