Analysis of thorium fuel feasibility in large scale gas cooled fast reactor using MCNPX code von Ibrahim, Amr, Aziz, Moustafa, EL-Kameesy, S.U., EL-Fiki, S.A., Galahom, A.A.

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The effect of homogenization on the neutronic parameters and transmutation of GFR-2400 fast reactor fuel assembly von Ibrahim, Amr, Aziz, Moustafa, EL-Fiki, S.A., EL-Kameesy, S.U., Galahom, A.A.

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A proposed design for security system for nuclear waste warehouses against terrorists attack von Wadoud, A.A., Abdelghafar Galahom, A., Abdel-Rahman, Mohamed A.E.

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