Neutron yield as a measure of achievement nuclear fusion using a mixture of deuterium and tritium isotopes von Youssef, Ahmed, Anwar, Rania, Bashter, Ibrahim I, Amin, Esmat A, Reda, Sonia M.

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Calculation of dose rates in loss of coolant accident due to double ended rupture of the experimental tangential irradiation beam tube of MTR reactor von AboElross, Mahmoud R., Amin, Esmat A., Zaky, Magdy M., Abdelsalam, A., Osman, W.

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Study of neutronic characteristics for the VVER reactor assembly with five various burnable poisons using MCNPX code von Reda, Sonia M., Elkhawas, Nourhan A., Amin, Esmat A.

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Computational study on distribution feasibility of radioactive waste transmutation in accelerator driven system von Al Qaaod, Amer, Pavlovych, Volodymyr, Ridikas, Danas, Gulik, Volodymyr, Amin, Esmat

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Neutronic Performance of the VVER-1000 Reactor Using Thorium Fuel with ENDF Library von Reda, Sonia M., Gomaa, Ibrahim M., Bashter, Ibrahim I., Amin, Esmat A.

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Effect of MOX fuel and the ENDF/B-VIII on the AP1000 neutronic parameters calculations by using MCNP6 von Reda, Sonia, Gomaa, Ibrahim, Bashter, Ibrahim, Amin, Esmat

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Rod ejection accident analysis for AP1000 with MOX/UOX mixed core loading von Selim, Hala K., Amin, Esmat H., Roushdy, Hassan E.

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Transmutation performance of uniform and nonuniform distributions of plutonium and minor actinides in TRIGA Mark II ADS reactor von Al Qaaod, Amer A., Shahbunder, Hesham, Refeat, R.M., Amin, Esmat A., El-Kameesy, S.U.

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Evaluation of subcritical multiplication parameters in MYRRHA-FASTEF accelerator driven system reactor von Al-Ssalahy, Hedarh M., Al Qaaod, Amer A., El-Kameesy, Samir U., Amin, Esmat A.

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Effects of Pu and MA uniform and nonuniform distributions on subcritical multiplication of TRIGA Mark II ADS reactor von Shahbunder, Hesham, Al Qaaod, Amer A., Amin, Esmat A., EL-Kameesy, S.U.

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Calculation of the NEA C5G7 MOX benchmark with MCNP5 von Reda, Sonia M., Amin, Esmat A.

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Investigation of subcritical multiplication parameters in TRIGA Mark II accelerator driven system von Shahbunder, Hesham, El-Kameesy, S.U., Amin, Esmat A., Al Qaaod, Amer A.

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Burnup and neutronic analysis for UOX and MOX fuel assemblies in VVER reactor von Louis, Heba K., Amin, Esmat

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MCNPX calculation of the reactivity worth of actinides OSMOSE samples von Shahbunder, Hesham I., Amin, Esmat H., El-Khameesy, Samir U., Hafez, Noura H.

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Utilizing even Plutonium Isotopes as burnable absorbers for controlling the reactivity and power distribution in Pressurized Water Reactors von Mustafa, Sayed Saeed, Amin, Esmat A.

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Evaluation of neutron radiation damage in the VVER-1200 reactor pressure vessel von Louis, Heba K., Ateya, Afaf A.E., Amin, Esmat

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Study on criticality and reactivity coefficients of VVER-1200 reactor von Hafez, Noura, Shahbunder, Hesham, Amin, Esmat, Elfiki, S.A., Abdel-Latif, A.

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The Effect of burnable absorbers on neutronic parameters of VVER-1200 reactor von Hafez, Noura, Shahbunder, Hesham, Amin, Esmat, El-Kamessy, S. U., Elfiki, S. A., Latef, Ahmed

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Comparison between the calculated and measured dose distributions for four beams of 6 MeV linac in a human-equivalent phantom von Reda, Sonia, Massoud, Eman, Bashter, Ibrahem, Amin, Esmat

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Determination of effects of burn up and reflector material on the kinetic parameters for open pool reactor using MCNP code von Shawer, M., Aly, N., Nagy, M., Amin, E.

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