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Gamma and neutron dosimetry in nuclear reactors by means of colored polyvinyl alcohol films

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Abstract

It is shown that polyvinyl alcohol films containing methylene blue which become discolored under the effects of radiation are suitable for gamma and neutron radiation dosimetry in nuclear reactors. The degree of discoloration varies linearly with the dose in the 104–106 rad range and, over a broad range of values, is practically independent of variations in linear energy transfer, dose rate, and temperature. Films containing boric acid in addition to the dye can be used for recording thermal-neutron doses in the 1012–1014 neutrons/cm2 range. The measurement error is within ±10% in every case.

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Translated from Atomnaya Énergiya, Vol. 19, No. 3, pp. 273–276, September, 1965.

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Lavrentovich, Y.I., Levon, A.I., Mel'nikova, G.N. et al. Gamma and neutron dosimetry in nuclear reactors by means of colored polyvinyl alcohol films. At Energy 19, 1189–1192 (1965). https://doi.org/10.1007/BF01127583

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  • DOI: https://doi.org/10.1007/BF01127583

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