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Keywords = MCNPX
Number of Articles: 6
Proposed New Different Coincidence Neutron Detection Systems using Monte Carlo Simulation.

Volume 57, Issue 3, July 2024, Pages 23-34

Rasha Ali El-Tayebany; Mootaz Ebied Shalaf

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Radiological Characterization and Safety during Decommissioning of aNuclear Reactor

Volume 56, Issue 2, January 2023, Pages 1-8

Rowayda Fayez Mahmoud Hegazy Abou Alo; Mohamed Shaat

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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.

Volume 55, Issue 1, January 2022, Pages 70-76

Mahmoud aboelross; esmat amin; Magdy Zaky; Abdallah Abdelsalam; Wafaa Osman Bahr

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Analysis of Fuel Burn-up Calculations of 3600 MWth Sodium cooled Fast Reactor Core

Volume 54, Issue 3, July 2021, Pages 108-114

Amr Ibrahim

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Development of Two Software Packages for Connecting with the MCNPX and NJOY Nuclear Codes to Directly Obtain and Extract Multi-Group Nuclear Cross Sections for Any Isotope

Volume 54, Issue 1, January 2021, Pages 120-133

Seyed Alireza Mousavi Shirazi

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Evaluation of ENDF/B-VI.8 and ENDF/B-VII.0 Nuclear Data Libraries using OSMOSE Samples of MINERVE Reactor

Volume 53, Issue 1, January 2020, Pages 163-171

Hesham Shahbunder

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Arab Journal of Nuclear Sciences and Applications
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