Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2018, Vol. 29 ›› Issue (4): 52 doi: 10.1007/s41365-018-0385-1

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Flux measurements for a DD neutron generator using neutron activation analysis

Walid A. Metwally 1 • Samar El-Sayed 1 • Ahmad Ababneh 1 • David L. Williams 2 • Allan X. Chen 2   

  1. 1 Department of Nuclear Engineering, University of Sharjah, Sharjah 27272, UAE
    2 Adelphi Technology, 2003 E Bayshore Rd., Redwood City, CA 94063, USA 123
  • Contact: Walid A. Metwally E-mail:WMetwally@sharjah.ac.ae
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Walid A. Metwally, Samar El-Sayed, Ahmad Ababneh, David L. Williams, Allan X. Chen. Flux measurements for a DD neutron generator using neutron activation analysis.Nuclear Science and Techniques, 2018, 29(4): 52     doi: 10.1007/s41365-018-0385-1
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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.

Key words: Neutron activation analysis, Neutron generator, Neutron moderation, Thermal neutron flux measurement