M. Z. Youssef

发表

Assessment and optimization of the interspace dose rate of the diagnostics equatorial port plug #3 in ITER with Attila

M. Z. Youssef, R. E. Feder, 2013, 2013 IEEE 25th Symposium on Fusion Engineering (SOFE).

ENGINEERING DESIGN OF THE SOLASE-H LASER FUSION HYBRID REACTOR.

Gregory A. Moses, Said I. Abdel-Khalik, I. N. Sviatoslavsky, 1800 .

Comparing the Prediction of “Attila” Code to the Experimental Data of Fusion Integral Experiments and to the Results of MCNP Code

M. Z. Youssef, P. Batistoni, L. Patrizzi, 2007 .

Uncertainties in Prediction of Tritium Breeding in Candidate Blanket Designs Due to Present Uncertainties in Nuclear Data Base

Mohamed A. Abdou, M. Z. Youssef, M. Abdou, 1986 .

Neutronics tests in a fusion engineering facility

Mohamed A. Abdou, M. Z. Youssef, 1989 .

Three-dimensional lattice calculations for a laser-fusion fissile-enrichment fuel factory

Said I. Abdel-Khalik, M. Z. Youssef, Magdi Ragheb, 1978 .

Neutronics scaling in fusion test devices

M. Z. Youssef, K. Shin, 1985 .

X–Ray Surface and Volumetric Heat Deposition and Tritium Breeding Issues in Liquid-Protected FW in High Power Density Devices

Neil B. Morley, M. Z. Youssef, Anter El-Azab, 1998 .

An overview of dual coolant Pb–17Li breeder first wall and blanket concept development for the US ITER-TBM design

Steven J. Zinkle, Neil B. Morley, Mohamed A. Abdou, 2006 .

Assessment of dose rate profiles and accessibility inside the building of the experimental fusion reactor, ITER, during operation and after shutdown

Mohamed A. Abdou, Anil Kumar, M. Z. Youssef, 1998 .

Utilization of Fission Reactors for Fusion Engineering Testing

G. A. Deis, L. G. Miller, M. Z. Youssef, 1985 .

Verification of ITER shielding capability and FENDL data benchmarking through analysis of bulk shielding experiment on large SS316/water assembly bombarded with 14 MeV neutrons

Hiroshi Maekawa, Mohamed A. Abdou, Yujiro Ikeda, 1998 .