Secondary Standardization of Neutron Fluence Fields at the Argonaut Reactor - IEN: Assessment of Calibration and Irradiation Metrological Capacity for Samples and Instruments

Autores/as

  • Felipe Souza da Silva ABNT
    • Walsan Wagner Pereira Instituto de Radioproteção e Dosimetria image/svg+xml
      • Conceptualización
      • Supervisión
      • Redacción - revisión y edición
    • Francisco José Oliveira Ferreira Nuclear Engineering Institute image/svg+xml
      • Conceptualización
      • Curación de datos
      • Redacción - revisión y edición
      • Supervisión

    DOI:

    https://doi.org/10.15392/2319-0612.2026.3068

    Palabras clave:

    Neutron Fluence, Bonner Spheres Spectrometry, Secondary Standardization, Dosimetry

    Resumen

    This article evaluates the secondary standardization of neutron fluence fields at the Argonaut Reactor of the Nuclear Engineering Institute (IEN). The study focused on the utilization of the Bonner Sphere Spectrometer (BSS) to determine the neutron spectrum at different positions of the lateral channel (plug 1) of the reactor, essential for characterizing radiation fields in complex environments. Measurements were conducted at varying distances (100 cm to 250 cm). The decrease in counts with increasing diameter indicated a higher presence of neutrons in the absorption energy range (0.1 eV to   2 MeV) for the 2", 3", and 5" spheres, but the 3" sphere exhibited different behavior, suggesting a greater presence of neutrons between 0.1 eV and 700 keV. As the BSS was moved away from the neutron source, the reduction in counts was expected. However, for the 8", 10", and 12" spheres, the analysis revealed a convergence of curves to a union of values between 0.1 eV and 6 MeV. These findings highlight the importance of precise neutron fluence characterization for dosimetric calibration. The data also serve as a basis for validating computational models in neutron metrology, contributing to the enhancement of nuclear research infrastructure. The Precision Long Counter (PLC) will be set up in future studies to complement BSS measurements, further advancing neutron detection capabilities.

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    Referencias

    [1] IEN - Relatório Final de Análise de Segurança do Reator Argonauta, 2023

    [2] Tavlet, M., et. al. The Importance of Standardization in Neutron Field Measurements. Nuclear Instruments and Methods in Physics Research Section A, Vol. 476, No. 1-2, pp. 236-244 (2002).

    [3] Zbořil, M., et. al. Characterisation of the PTB Thermal Neutron Calibration Facility with the Bonner Sphere Spectrometer NEMUS. Radiation Protection Dosimetry, Vol. 180, No. 1–4, pp. 98–101 (2018). DOI: https://doi.org/10.1093/rpd/ncx242

    [4] Konno, C., et. al. Validation of Neutron Spectrum Unfolding Using Bonner Sphere Spectrometers. Journal of Nuclear Science and Technology, Vol. 38, No. 12, pp. 1050-1056 (2001).

    [5] Mihaila, B., et. al. Neutron Field Characterization in Reactor Experiments Using Bonner Sphere Spectrometer. Annals of Nuclear Energy, Vol. 65, pp. 200-210 (2014).

    [6] Kimura, Y., et. al. Application of Bonner Sphere Spectrometer in Neutron Dosimetry for Reactor Environments. Progress in Nuclear Energy, Vol. 90, pp. 205-212 (2016).

    [7] ICRP. Neutron Fluence-to-Dose Equivalent Conversion Coefficients. ICRP Publication 74, Annals of the ICRP, Vol. 26, No. 3-4, pp. 1-206 (1996). DOI: https://doi.org/10.1016/S0146-6453(96)90005-6

    [8] Bartlett, D. T. A Review of Neutron Spectrometry for Radiation Protection Dosimetry. Radiation Protection Dosimetry, Vol. 110, No. 4, pp. 367-374 (2004). DOI: https://doi.org/10.1093/rpd/nch131

    [9] Alevra, A. V., et al. Neutron Metrology Using Bonner Spheres: An Overview. Metrologia, Vol. 37, No. 6, pp. 565-578 (2000).

    [10] Dumitru, I., et. al. Validation of Computational Neutron Transport Models with Bonner Sphere Spectrometer Data. Radiation Measurements, Vol. 45, No. 10, pp. 1186-1192 (2010).

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    Publicado

    2026-09-11

    Declaración de disponibilidad de datos

    The data that support the findings of this study are available from the corresponding author, subject to institutional authorization from the Nuclear Engineering Institute (IEN).

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    Sección

    Original Articles