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Improved method for measuring the γ-ray absorbed dose rate in models of iron shielding of a thermonuclear reactor

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Abstract

An improved method of measuring the absorbed γ-ray dose rate usingCaSO 4 andSrSO 4 type thermoluminescent detectors in models of iron shielding of a thermonuclear reactor is described. The reactionT(d, n)4 He served as a neutron source. The method obtained makes it possible to determine the absorbed γ-ray dose rate in shielding without using computed information and relying only on experimental data on the rates of nuclear reactions in threshold detectors. 7 figures, 1 table, 9 references.

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Authors
  1. M. I. Andreev
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  2. V. V. Afanas’ev
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  3. A. G. Belevitin
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  4. V. L. Romodanov
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Additional information

Moscow Engineering-Physics Institute. Translated from Atomnaya Énergiya, Vol. 86, No. 3, pp. 219–225, March, 1999.

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Andreev, M.I., Afanas’ev, V.V., Belevitin, A.G. et al. Improved method for measuring the γ-ray absorbed dose rate in models of iron shielding of a thermonuclear reactor. At Energy 86, 222–228 (1999). https://doi.org/10.1007/BF02672951

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  • DOI: https://doi.org/10.1007/BF02672951

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