Improved method for measuring the absorbed dose rate of gamma radiation in the models of iron shield of a thermonuclear reactor

被引:0
|
作者
Andreev, M.I. [1 ]
Afanas'ev, V.V. [1 ]
Belevitin, A.G. [1 ]
Romodanov, V.L. [1 ]
机构
[1] MIFI, Moscow, Russia
来源
Atomnaya Energiya | 1999年 / 86卷 / 03期
关键词
Dosimeters - Dosimetry - Gamma rays - Iron - Models - Neutrons - Radiation shielding - Thermoluminescence;
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学科分类号
摘要
An improved method for measuring the absorbed dose rate (ADR) of gamma radiation by the thermoluminescent dosimeters of the CaSO4 and SrSO4 type in the models of iron shield of a thermonuclear reactor is described. The T(d,n) 4He reaction is a neutron source. The developed method makes it possible to determine the ADR of gamma radiation only on the basis of experimental data on the nuclear reaction rate of threshold detectors without using calculational data.
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页码:219 / 225
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