Abderrafi M. Ougouag

Affiliations: 
Idaho State University, Pocatello, ID, United States 
Area:
Nuclear Engineering, Computer Science
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"Abderrafi Ougouag"
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Publications

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Akbas S, Martinez-Quiroga V, Aydogan F, et al. (2019) Thermal-hydraulics and neutronic code coupling for RELAP/SCDAPSIM/MOD4.0 Nuclear Engineering and Design. 344: 174-182
Marquez MG, Ougouag AM, Petrovic B. (2017) Model for radiation damage-induced grain subdivision and its influence in U3Si2 fuel swelling Annals of Nuclear Energy. 145: 105712
Ouisloumen M, Ougouag AM, Ghrayeb SZ. (2015) Anisotropic elastic resonance scattering model for the neutron transport equation Nuclear Science and Engineering. 179: 59-84
Martinez-Quiroga V, Akbas S, Aydogan F, et al. (2015) Coupling of RELAP5-SCDAP MOD4.0 and neutronic codes Asme International Mechanical Engineering Congress and Exposition, Proceedings (Imece). 6
Akbas S, Martinez-Quiroga V, Aydogan F, et al. (2015) Survey of coupling schemes in traditional coupled neutronics and thermal-hydraulics codes Asme International Mechanical Engineering Congress and Exposition, Proceedings (Imece). 6
Ghrayeb SZ, Ougouag AM, Ouisloumen M, et al. (2014) Multi-group formulation of the temperature-dependent resonance scattering model and its impact on reactor core parameters Annals of Nuclear Energy. 63: 751-762
Zhang D, Rahnema F, Ougouag AM. (2013) A local incident flux response expansion transport method for coupling to the diffusion method in cylindrical geometry Nuclear Science and Engineering. 175: 70-80
Hiruta M, Johnson G, Rostamian M, et al. (2013) Computational and experimental prediction of dust production in pebble bed reactors, Part II Nuclear Engineering and Design. 263: 509-514
Rostamian M, Johnson G, Hiruta M, et al. (2013) Computational and experimental prediction of dust production in pebble bed reactors-Part I Nuclear Engineering and Design. 263: 500-508
Sen RS, Pope MA, Ougouag AM, et al. (2013) Assessment of possible cycle lengths for fully encapsulated microstructure fueled light water reactor concepts Nuclear Engineering and Design. 255: 310-320
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