Neutron dose estimation in a zero power nuclear reactor

This work presents the characterization and contribution of neutron and gamma components to the absorbed dose in a zero power nuclear reactor. A dosimetric method based on Fricke gel was implemented to evaluate the separation between dose components in the mixed field. The validation of this propose...

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Bibliographic Details
Published in:Radiation physics and chemistry (Oxford, England : 1993) England : 1993), 2016-10, Vol.127, p.62-67
Main Authors: Triviño, S., Vedelago, J., Cantargi, F., Keil, W., Figueroa, R., Mattea, F., Chautemps, A., Santibañez, M., Valente, M.
Format: Article
Language:English
Subjects:
Fricke gel dosimetry
MCNP
Monte Carlo simulations
Thermal/epithermal neutron flux
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Summary:This work presents the characterization and contribution of neutron and gamma components to the absorbed dose in a zero power nuclear reactor. A dosimetric method based on Fricke gel was implemented to evaluate the separation between dose components in the mixed field. The validation of this proposed method was performed by means of direct measurements of neutron flux in different positions using Au and Mg-Ni activation foils. Monte Carlo simulations were conversely performed using the MCNP main code with a dedicated subroutine to incorporate the exact complete geometry of the nuclear reactor facility. Once nuclear fuel elements were defined, the simulations computed the different contributions to the absorbed dose in specific positions inside the core. Thermal/epithermal contributions of absorbed dose were assessed by means of Fricke gel dosimetry using different isotopic compositions aimed at modifying the sensitivity of the dosimeter for specific dose components. Clear distinctions between gamma and neutron capture dose were obtained. Both Monte Carlo simulations and experimental results provided reliable estimations about neutron flux rate as well as dose rate during the reactor operation. Simulations and experimental results are in good agreement in every positions measured and simulated in the core. •Dose components in a neutron mixed field were characterized using Fricke dosimetry.•Dedicated MCNP routine were developed to perform dosimetry in RA-0 mixed field.•Results were successfully compared with activation foils measurements.
ISSN:0969-806X
1879-0895
DOI:10.1016/j.radphyschem.2016.06.011