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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