Zobrazeno 1 - 10 of 30 pro vyhledávání: '"Ouadie, KABACH"'
1
Akademický článek
Calculations of the principal neutronic characteristics of a hypothetical VVER assembly with minor actinides incorporated into PuO2-ThO2 fuel in a duplex configuration
Autor: Achraf Radi, Ouadie Kabach, El Mahjoub Chakir
Publikováno v: Nuclear Energy and Technology, Vol 10, Iss 4, Pp 221-233 (2024)
The VVER-1200/AES-2006 is recognized as a leading Gen III+ nuclear reactor design, meeting stringent international safety standards. This study evaluates the use of a novel PuO2-ThO2 duplex fuel, incorporating weapon-grade plutonium (WgPu) and thoriu
Externí odkaz: https://doaj.org/article/9dba903d98b643fab15951f174ba961f
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2
Akademický článek
Analyzing (Th-233U-235U)O2 fuel performance in various assembly configurations: A comparative neutronic study
Autor: Fadi El Banni, Bogbe L. H. Gogon, Ouadie Kabach, El Mahjoub Chakir
Publikováno v: Nuclear Energy and Technology, Vol 10, Iss 3, Pp 169-178 (2024)
This article investigates alternate fuel options for Pressurized Water Reactors (PWRs), focusing on thorium use to address safety, efficiency, and waste issues associated with standard UO2 fuel. Challenges in thorium utilization, such as the lack of
Externí odkaz: https://doaj.org/article/b48b8dc1a8d44ff6948f235a17355354
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3
Akademický článek
An inter-comparison between ENDF/B-VIII.0-NECP-Atlas and ENDF/B-VIII.0-NJOY results for criticality safety benchmarks and benchmarks on the reactivity temperature coefficient
Autor: Ouadie Kabach, Abdelouahed Chetaine, Abdelfettah Benchrif, Hamid Amsil
Publikováno v: Nuclear Engineering and Technology, Vol 53, Iss 8, Pp 2445-2453 (2021)
Since the nuclear data forms a vital component in reactor physics computations, the nuclear community needs processing codes as tools for translating the Evaluated Nuclear Data Files (ENDF) to simulate nuclear-related problems such as an ACE format t
Externí odkaz: https://doaj.org/article/30b3d970035b4fd2816f38447d92ea0a
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4
Akademický článek
Neutronic feasibility study of (Th-233U)-ZrH1.65 fuel in a modelled TRIGA research reactor
Autor: Fadi El Banni, Ouadie Kabach, Aka A. Koua, Bogbe L.H. Gogon, Georges A. Monnehan, Abdelfettah Benchrif, Hamid Amsil, Abdelouahed Chetaine
Publikováno v: Journal of King Saud University: Science, Vol 34, Iss 2, Pp 101769- (2022)
This paper presents a comparative analysis when transitioning from fuel meat based on uranium zirconium hydride (U-ZrH1.65) to one based on thorium-uranium-233 zirconium hydride ((Th-233U)-ZrH1.65) as an alternative option for TRIGA reactors. The aim
Externí odkaz: https://doaj.org/article/f89456fb7a004afb9e3f1222b539e32b
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6
Akademický článek
Physical Protection System, Corrective Actions, and Weaknesses Identification Based on Nuclear Security Series: The Hypothetical Atomic Research Institute (HARI) Case
Autor: Ouadie Kabach, Abdelouahed Chetaine, Abdelfettah Benchrif
Publikováno v: International Journal of Nuclear Security, Vol 6, Iss 1 (2020)
The paper is an attempt, based on the IAEA’s Nuclear Security Series (NSS), to identify any unacceptable dysfunction of Physical Protection System (PPS) of the Material Test Reactor (MTR) facility in a Hypothetical Atomic Research Institute (HARI).
Externí odkaz: https://doaj.org/article/9105b58a0070403bbb79b8da9d32a8a4
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