Amanote Research
Register
Sign In
Discover open access scientific publications
Search, annotate, share and cite publications
Publications by Randa Mahmoud
Design of Portable Shield for Neutron Sources Using McNp Computer Code
Arab Journal of Nuclear Sciences and Applications
Related publications
Gamma Shield Design for Primary Coolant Sources Using the Ibm Type 650 Computer
Portable Neutron Detector Using Ce:LiCaAlF6 Scintillator
Sensors and Materials
Materials Science
Instrumentation
Advanced Neutron Sources: Plant Design Requirements
Inspect: An Interactive Computer Code for Unfolding Neutron Spectra From Activation Measurements.
The Experience of Using Portable Russian Neutron Generator for Gamma-Neutron Therapy of Domestic Animals With Malignant Tumors
Radiation and Risk
Nuclear Medicine
Radiology
Nuclear
Public Health
Radiation
High Energy Physics
Environmental
Imaging
Occupational Health
Application of Dose Evaluation of the McNp Code for the Spent Fuel Transport Cask
Progress in Nuclear Science and Technology
Approach for Calculating Population Doses Using the CIDER Computer Code
Spallation Neutron Sources
Pulsed Neutron Sources for Neutron Crystallography: New and Future Capabilities
Acta Crystallographica Section A Foundations of Crystallography