Keywords = MCNPX code
Analysis of Optimum Accident Tolerant Fuel and Cladding Behavior in Advanced Pressurized Water Reactor

Volume 57, Issue 1, January 2024, Pages 120-126

Moustafa Abdelwahab Aziz; Neama Mohammed El-Sahlamy

Decommissioning Plan and Cost Estimation of TRICOII Research Reactor

Volume 55, Issue 3, July 2022, Pages 10-20

Heritier Beya Tshitenge; Rowayda Fayez Mahmoud; Ahmed Emad El-Din El-Saghir; Alya Adel Badawi; Mohamed K Shaat

Evaluation of gamma rays shielding competence for bentonite clay /PVA polymer matrix using MCNPX code

Volume 53, Issue 2, April 2020, Pages 177-188

fawzy hammad sallam; Ibrahim Zaki Hager; Yasser saad Rammah; Hosam Ahmed Othman; Eman Mohamed Ibrahim; sayed Fahmy Hassan; Zakaria Ahmed