Comparative Study of Thermal Neutron Flux from Gold Foil Activation.

Authors

  • Watila Lins Silva Institute of Radiation Protection and Dosimetry image/svg+xml
    • Max Ramos Santos Mestre Institute of Radiation Protection and Dosimetry image/svg+xml
      • Regio Gomes Santos Institute of Radiation Protection and Dosimetry image/svg+xml
        • Achiles Astuto Federal University of Rio de Janeiro image/svg+xml
          • Walsan Pereira Wagner Institute of Radiation Protection and Dosimetry image/svg+xml

            DOI:

            https://doi.org/10.15392/2319-0612.2026.2712

            Keywords:

            Thermal Neutron Fluence, Gold Foil Activation, MCNP-5, Gamma Spectrometry, Neutron Dosimetry, Metrology, TNF2, C/E Analysis

            Abstract

            This study presents a comparative analysis between Monte Carlo simulations (MCNP-5) and experimental measurements of thermal neutron fluence using gold foil activation at the TNF2 irradiation facility of the Neutron Metrology Laboratory (LNMRI/IRD). The MCNP-5 model was constructed to replicate the irradiator geometry and source configuration. Gold foils, both bare and cadmium-covered, were irradiated and analyzed via gamma spectrometry to determine the induced activity of 198Au. The results of the calculated nuclear reaction rates were compared to the measured activities through C/E (Calculated/Experimental) analysis. The findings show consistent agreement within experimental uncertainty, supporting the accuracy of the MCNP model and reinforcing the role of TNF2 in the national and international metrological infrastructure for neutron dosimetry. Future developments will include improvements in flux mapping and personal dosimetry applications.

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            References

            [1] ASTUTO, A; FERNANDES, S S; PATRÃO, K C S; FONSECA, E S; PEREIRA, W W; LOPES, R T. Improvements in the thermal neutron calibration unit, TNF2, at LNMRI/IRD. Radiation Protection Dosimetry, v. 180, p. 56-61, 2018. DOI: https://doi.org/10.1093/rpd/ncy028

            [2] ASTUTO, A., PATRÃO, K.C.S., FONSECA, E.S., PEREIRA, W.W., LOPES, R.T., Polyethylene filter for the TNF2 thermal neutron facility. Radiation Protection Dosimetry, v. 199, p. 187-190, 2023. DOI: https://doi.org/10.1093/rpd/ncac255

            [3] ASTUTO, A., Desenvolvimento de um sistema de irradiação com nêutrons térmicos para calibração de monitores. Tese Doutorado. COPPE, Rio de Janeiro, Brasil, 2016.

            [4] FOSBERG, L., Neutron cross section for aluminium. AE-117, Aktiebolaget Atomenergi, Stockholm, Sweden,1963.

            [5] JAFARI, M.; JAFARI, H.; MOKHTARI, J. Characterization of the PGNAA neutron beam of Isfahan MNSR through the calculations and different measurement methods. Measurement, v, 241, p 1-8, 2025. DOI: https://doi.org/10.1016/j.measurement.2024.115704

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            Published

            2026-01-30

            Issue

            Vol. 14 No. 1 (2026)

            Section

            INAC/ENAN 2024

            Categories

            License

            Copyright (c) 2026 Watila Lins Silva, Max Ramos, Regio Santos Gomes, Achiles Astuto, Walsan Wagner Pereira

            Creative Commons License

            This work is licensed under a Creative Commons Attribution 4.0 International License.

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