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Flux measurements for a DD neutron generator using neutron activation analysis

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Abstract

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.

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Authors and Affiliations

  1. Department of Nuclear Engineering, University of Sharjah, Sharjah, 27272, UAE

    Walid A. Metwally, Samar El-Sayed & Ahmad Ababneh

  2. Adelphi Technology, 2003 E Bayshore Rd., Redwood City, CA, 94063, USA

    David L. Williams & Allan X. Chen

Authors
  1. Walid A. Metwally
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  2. Samar El-Sayed
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  3. Ahmad Ababneh
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  4. David L. Williams
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  5. Allan X. Chen
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Correspondence to Walid A. Metwally.

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Metwally, W.A., El-Sayed, S., Ababneh, A. et al. Flux measurements for a DD neutron generator using neutron activation analysis. NUCL SCI TECH 29, 52 (2018). https://doi.org/10.1007/s41365-018-0385-1

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  • DOI: https://doi.org/10.1007/s41365-018-0385-1

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