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.
Details
- Design, Construction, and Modeling of a 252Cf Neutron Irradiator
- Anderson, Blake (Author)
- Holbert, Keith (Author)
- Bowler, Herbert (Author)
- Ira A. Fulton Schools of Engineering (Contributor)
- Digital object identifier: 10.1155/2016/9012747
- Identifier TypeInternational standard serial numberIdentifier Value1687-6075
- Identifier TypeInternational standard serial numberIdentifier Value1687-6083
- View the article as published at https://www.hindawi.com/journals/stni/2016/9012747/, opens in a new window
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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