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Quantitative comparison between PGNAA measurements and MCNPX simulations

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Abstract

A MCNPX model of a neutron activation facility for radioactive waste characterization was built to support experimental studies. To validate this model, small samples of different elemental composition were irradiated and experimental data are compared to simulation results obtained using different neutron capture prompt gamma ray databases. The different databases employed lead to similar results. Simulated and measured net peak areas agree within ±20 %.

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Authors and Affiliations

  1. Cadarache, Nuclear Measurement Laboratory, CEA, DEN, 13108, Saint-Paul-lez-Durance, France

    T. Nicol, C. Carasco, B. Perot, J. L. Ma & E. Payan

  2. Institute for Energy and Climate Research – Nuclear Waste Management and Reactor Safety, FZJ, Wilhelm-Johnen-Straße, 52428, Jülich, Germany

    T. Nicol, E. Mauerhofer & A. Havenith

  3. Laboratoire de Physique Subatomique et de Cosmologie, Université Grenoble Alpes, CNRS/IN2P3, Grenoble, France

    J. Collot

Authors
  1. T. Nicol
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  2. C. Carasco
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  3. B. Perot
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  4. J. L. Ma
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  5. E. Payan
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  6. E. Mauerhofer
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  7. A. Havenith
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  8. J. Collot
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Correspondence to E. Mauerhofer.

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Nicol, T., Carasco, C., Perot, B. et al. Quantitative comparison between PGNAA measurements and MCNPX simulations. J Radioanal Nucl Chem 308, 671–677 (2016). https://doi.org/10.1007/s10967-015-4451-4

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  • DOI: https://doi.org/10.1007/s10967-015-4451-4

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