Design, Construction, and Modeling of a 252Cf Neutron Irradiator

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 compa...

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Main Authors: Blake C. Anderson, Keith E. Holbert, Herbert Bowler
Format: Article
Language:English
Published: Wiley 2016-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2016/9012747
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author Blake C. Anderson
Keith E. Holbert
Herbert Bowler
author_facet Blake C. Anderson
Keith E. Holbert
Herbert Bowler
author_sort Blake C. Anderson
collection DOAJ
description 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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series Science and Technology of Nuclear Installations
spelling doaj-art-0fe0a655b23444a6b63cefa84f3977512025-08-20T02:02:32ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832016-01-01201610.1155/2016/90127479012747Design, Construction, and Modeling of a 252Cf Neutron IrradiatorBlake C. Anderson0Keith E. Holbert1Herbert Bowler2Arizona State University, Tempe, AZ 85287-5706, USAArizona State University, Tempe, AZ 85287-5706, USAArizona State University, Tempe, AZ 85287-5706, USANeutron 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.http://dx.doi.org/10.1155/2016/9012747
spellingShingle Blake C. Anderson
Keith E. Holbert
Herbert Bowler
Design, Construction, and Modeling of a 252Cf Neutron Irradiator
Science and Technology of Nuclear Installations
title Design, Construction, and Modeling of a 252Cf Neutron Irradiator
title_full Design, Construction, and Modeling of a 252Cf Neutron Irradiator
title_fullStr Design, Construction, and Modeling of a 252Cf Neutron Irradiator
title_full_unstemmed Design, Construction, and Modeling of a 252Cf Neutron Irradiator
title_short Design, Construction, and Modeling of a 252Cf Neutron Irradiator
title_sort design construction and modeling of a 252cf neutron irradiator
url http://dx.doi.org/10.1155/2016/9012747
work_keys_str_mv AT blakecanderson designconstructionandmodelingofa252cfneutronirradiator
AT keitheholbert designconstructionandmodelingofa252cfneutronirradiator
AT herbertbowler designconstructionandmodelingofa252cfneutronirradiator