Modelisation and distribution of neutron flux in radium–beryllium source (226Ra–Be)

Using the Monte Carlo N-Particle code (MCNP-6), to analyze the thermal, epithermal and fast neutron fluxes, of 3 millicuries of radium–beryllium, for determine the qualitative and quantitative of many materials, using method of neutron activation analysis. Radium–beryllium source of neutron is estab...

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Bibliographic Details
Published inMoscow University physics bulletin Vol. 72; no. 5; pp. 465 - 469
Main Authors Didi, Abdessamad, Dadouch, Ahmed, Jai, Otman
Format Journal Article
LanguageEnglish
Published Moscow Pleiades Publishing 01.09.2017
Springer Nature B.V
Subjects
Beryllium
Computer simulation
Irradiation
Mathematical and Computational Physics
Neutron activation analysis
Neutron flux
Neutrons
Nuclear physics
Physics
Physics and Astronomy
Physics of Nuclei and Elementary Particles
Qualitative analysis
Radium
Radium 226
Theoretical
neutron flux radium–beryllium source
thermal neutrons
NAA
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Summary:Using the Monte Carlo N-Particle code (MCNP-6), to analyze the thermal, epithermal and fast neutron fluxes, of 3 millicuries of radium–beryllium, for determine the qualitative and quantitative of many materials, using method of neutron activation analysis. Radium–beryllium source of neutron is established to practical work and research in nuclear field. The main objective of this work was to enable us harness the profile flux of radium–beryllium irradiation, this theoretical study permits to discuss the design of the optimal irradiation and performance for increased the facility research and education of nuclear physics.
ISSN:0027-1349
1934-8460
DOI:10.3103/S0027134917050034