Flux measurements for a DD neutron generator using neutron activation analysis

  • Walid A. Metwally
  • Samar El-Sayed
  • Ahmad Ababneh
  • David L. Williams
  • Allan X. Chen


The fast and maximum thermal neutron fluxes from the DD-109 neutron generator at the University of Sharjah were experimentally measured by the activation technique using different neutron reactions. The thermal and fast neutron fluxes were found to be 2.960 × 106 and 6.186 × 107 n/cm2 s, respectively. This was done to verify the modeling results for the optimum moderator thickness needed to maximize the thermal neutron flux. The optimum moderator thickness was found to be between 3.5 and 4 cm. The present data were compared with the detailed MCNP model-based calculation performed in earlier work to simulate the generator.


Neutron activation analysis Neutron generator Neutron moderation Thermal neutron flux measurement 


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Copyright information

© Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Chinese Nuclear Society, Science Press China and Springer Nature Singapore Pte Ltd. 2018

Authors and Affiliations

  • Walid A. Metwally
    • 1
  • Samar El-Sayed
    • 1
  • Ahmad Ababneh
    • 1
  • David L. Williams
    • 2
  • Allan X. Chen
    • 2
  1. 1.Department of Nuclear EngineeringUniversity of SharjahSharjahUAE
  2. 2.Adelphi TechnologyRedwood CityUSA

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