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Development of a fast-pneumatic sample transfer system for DT neutron activation analysis at the University of Michigan

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Abstract

The development of an automated pneumatic transfer system used to quickly acquire data from materials irradiated with a deuterium–tritium (DT) neutron generator is described in this paper. This system was designed to gather data on short-lived activation and fast-fission products, and was used to characterize the generator’s neutron field. The average sample transit time between irradiation and data acquisition is 363.9 ms at an average velocity of 30.92 m/s (101.3 ft/s). The neutron flux profile as a function of depth into the sample capsule is shown to decrease exponentially, having a maximum flux value of 5.662 × 108 ± 0.056 × 108 n/cm2 s. The average DT neutron energy in the system’s sample geometry was determined to be 14.250 ± 0.011 MeV using a unique zirconium–niobium “sandwich” technique. A flux surface equation is also presented as a function of accelerator voltage and deuterium beam current. Methods of analysis are discussed with a proof of a linear flux profile assumption for thin foils.

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Authors and Affiliations

  1. Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI, 48109, USA

    A. B. Cusick, M. E. Morell-Gonzalez & M. R. Hartman

  2. Materials Science and Engineering, University of Michigan, Ann Arbor, MI, 48109, USA

    A. B. Cusick

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  1. A. B. Cusick
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  2. M. E. Morell-Gonzalez
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  3. M. R. Hartman
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Correspondence to A. B. Cusick.

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Cusick, A.B., Morell-Gonzalez, M.E. & Hartman, M.R. Development of a fast-pneumatic sample transfer system for DT neutron activation analysis at the University of Michigan. J Radioanal Nucl Chem 302, 1137–1141 (2014). https://doi.org/10.1007/s10967-014-3384-7

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  • DOI: https://doi.org/10.1007/s10967-014-3384-7

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