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Neutron production methods are an integral part of research and analysis for an array of applications. This paper examines methods of neutron production, and the advantages of constructing a radioisotopic neutron irradiator assembly using 252Cf. Characteristic neutron behavior and cost-benefit

Neutron production methods are an integral part of research and analysis for an array of applications. This paper examines methods of neutron production, and the advantages of constructing a radioisotopic neutron irradiator assembly using 252Cf. Characteristic neutron behavior and cost-benefit comparative analysis between alternative modes of neutron production are also examined. The irradiator is described from initial conception to the finished design. MCNP modeling shows a total neutron flux of 3 × 105 n/(cm2·s) in the irradiation chamber for a 25 μg source. Measurements of the gamma-ray and neutron dose rates near the external surface of the irradiator assembly are 120 μGy/h and 30 μSv/h, respectively, during irradiation. At completion of the project, total material, and labor costs remained below $50,000.

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    Title
    • Design, Construction, and Modeling of a 252Cf Neutron Irradiator
    Contributors
    Date Created
    2016-07-31
    Resource Type
  • Text
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    Identifier
    • Digital object identifier: 10.1155/2016/9012747
    • Identifier Type
      International standard serial number
      Identifier Value
      1687-6075
    • Identifier Type
      International standard serial number
      Identifier Value
      1687-6083
    Note
    • View the article as published at https://www.hindawi.com/journals/stni/2016/9012747/

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    Anderson, B. C., Holbert, K. E., & Bowler, H. (2016). Design, Construction, and Modeling of a252Cf Neutron Irradiator. Science and Technology of Nuclear Installations, 2016, 1-12. doi:10.1155/2016/9012747

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