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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 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.
- Anderson, Blake (Author)
- Holbert, Keith (Author)
- Bowler, Herbert (Author)
- Ira A. Fulton Schools of Engineering (Contributor)
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
- 2017-07-12 12:10:57
- 2021-10-27 01:30:15
- 3 years ago