Application of the Fricke Chemical Dose Meter and its Modifications for Dosimetry of Gamma-Neutron Radiation of a Pulse Reactor
The authors of the paper have studied the characteristics of the Fricke chemical dosimeter (of the standard composition (D1), without adding NaCl to the solution (D2), without NaCl and with a 10-fold increased concentration of Fe2+ (D3)) under irradiation with a dose rate up to 7⋅108 Gy/min at the BARS-6 burst-type reactor with two unshielded active zones operating either in a single pulse (65 – 70 μ s) mode or in a stationary (≈ 1 h) mode.
The dosimeter radiosensitivity (i.e., optical density per Gray) depended linearly on the dose of γ-neutron radiation in the range of 25 – 750 Gy, and was 1.96 ± 0.05 μGy–1 (D1), 2.04 ± 0.05 μGy–1 (D2), 2.08 ± 0.5 μ Gy–1 (D3) in the continuous irradiation mode and 1.24 ± 0.05μGy–1, 2.00 ± 0.05 μGy–1, 1.94 ± 0.05 μGy–1 in the pulse mode, respectively. It was ≈ 60% of their sensitivity to γ-radiation of 60Со (3.40 ± 0.02 μGy–1), but for a standard Fricke dosimeter irradiated in the pulsed mode, it was 1.6 times less, i.e., 36%. The experimental value of Gn(Fe3+) for all the solutions and both modes of irradiation varied insignificantly and averaged 0.84 ± 0.11 μM/J except for the standard solution in the pulsed mode (0.66 ± 0.07 μ M/J). The neutron doses determined by chemical and activation dosimeters agreed within the error limits, but the former were systematically higher by ≈ 20%.
Thus, in the range of neutron dose rates of the fission spectrum of 0.4 – 7⋅108 Gy/min, the effect of the dose rate is absent both in the standard version of the Fricke dosimeter (without NaCl) and in the modified version (with an increased concentration of Fe2+ ions). It makes possible to use the modified Fricke dosimeter for assessing the physical and dosimetric characteristics of mixed γ-neutron radiation beams with very high intensities.
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Link for citing the article: Potetnya V.I., Koryakina E.V., Troshina M.V., Koryakin S.N. Application of the Fricke Chemical Dose Meter and its Modifications for Dosimetry of Gamma-Neutron Radiation of a Pulse Reactor. Izvestiya vuzov. Yadernaya Energetika. 2021, no. 2, pp. 106-116; DOI: https://doi.org/10.26583/npe.2021.2.10 (in Russian).