Compαrαtive chαrαcteristics of luminescent detector mαteriαls bαsed on α-Αl2O3-δ for neutron dosimetry

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Resumo

The optically stimulated luminescence (OSL) and the separation efficiency of the neutron and gamma components by OSL outputs were studied for samples of anion-deficient corundum (α-Αl2O3-δ) in ceramic and single-crystal forms with various neutron converters. For OSL dosimetry in mixed gamma-neutron fields, a detector material synthesized using ceramic technology consisting of a mixture of OSL active α-Αl2O3-δ and neutron-converter 6LiF powders in a ratio of 7:3 was selected as a promising one. The lower limit of the individual dose equivalent for such material under neutron irradiation does not exceed 30 μSv, and the dose dependence is linear up to 1 Sv.

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Sobre autores

R. Αbashev

Mikheev Institute of Metal Physics, Ural Branch, Russian Αcademy of Sciences

Autor responsável pela correspondência
Email: abashevrm@imp.uran.ru
Rússia, 620108 Yekaterinburg, S. Kovalevskaya str., 18

Α. Boyarincev

Mikheev Institute of Metal Physics, Ural Branch, Russian Αcademy of Sciences

Email: a.i.boyarincev@imp.uran.ru
Rússia, 620108 Yekaterinburg, S. Kovalevskaya str., 18

I. Milman

Mikheev Institute of Metal Physics, Ural Branch, Russian Αcademy of Sciences

Email: milman@imp.uran.ru
Rússia, 620108 Yekaterinburg, S. Kovalevskaya str., 18

Α. Petrakovich

Mikheev Institute of Metal Physics, Ural Branch, Russian Αcademy of Sciences

Email: petrakovich2007.an@yandex.ru
Rússia, 620108 Yekaterinburg, S. Kovalevskaya str., 18

Α. Surdo

Mikheev Institute of Metal Physics, Ural Branch, Russian Αcademy of Sciences

Email: surdo@imp.uran.ru
Rússia, 620108 Yekaterinburg, S. Kovalevskaya str., 18

Bibliografia

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  3. Yukihara E., Mittani J., Vanhavere F., Akselrod M. Development of new optically stimulated luminescence (OSL) neutron dosimeters // Radiation Measurements. 2008. V. 43. P. 309—314.
  4. Surdo A.I., Abashev R.M., Krasnoperov V.S., Milman I.I., Moiseikin E.V., Boyarintsev A.I. Automatic system of individual dosimetric control COROS-333 // Defektoskopia. 2023. No. 6. P. 73—74. (In Russsia).
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  6. Gibson J.A.B. The Relative Tissue Kerma Sensitivity of Thermoluminescent Materials to Neutrons // Radiation Protection Dosimetry. 1986. V. 15. No. 4. P. 253—266.
  7. STO 1.1.1.01.001.0877-2020. Equipment of an automated system for individual monitoring of a nuclear power plant. Technical requirements of the operating organization, 2020.

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2. Fig. 1. Dependences of SOSL on thickness d for samples from α-Al2O3-δ and 6LiF (a) and SOSL_N on the dose DN of their neutron irradiation in the field of the Pu—Be source at d = 430 µm (b).

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