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New design of thermal neutron flux distribution of Am–Be neutron source irradiation in the paraffin moderator using MCNP-6

2015/11/29 by Abdessamad Didi, Jaouad Tajmouati, Didi, Abdessamad +7
Engineering · Physics and Astronomy · #Am–Be #Flux #L’ISTA #MCNP #NAA #Neutron #Neutron flux Americium-Beryllium #Nuclear Physics and Applications #Nuclear reactor physics and engineering #Paraffin #Radiation Detection and Scintillator Technologies #Thermal Neutrons

paper · doi:10.48317/imist.prsm/morjchem-v4i2.4119

openalex publication_date 2015/11/29 · openalex created_date 2025/10/10 · openalex updated_date 2026/07/01

Abstract

to increase the neutron flux Americium-Beryllium activity 20 Ci, source is centric to the center in a paraffin castle, our study is proposed a design prototype of the source, which has two parallel barriers beryllium, for to increase the radial flux from the source, fast neutrons are slowed in paraffin we used Monte Carlo code MCNP-6 for simulation, results analysis and was found with interpreting graphs is compared with other studies, we noticed that the neutron flux increasing (2.2 ± 0.0007) × 106 n/cm²s, this result is more improved than previous studies.

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