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

被引：1

作者：

Andreev, MI ^{[1
]}

Afanas'ev, VV ^{[1
]}

Belevitin, AG ^{[1
]}

Romodanov, VL ^{[1
]}

机构：

[1] Moscow Phys Engn Inst, Moscow, Russia

来源：

ATOMIC ENERGY | 1999年 / 86卷 / 03期

关键词：

Dose Rate; Thermonuclear Reactor; Neutron Source; Neutron Energy; Neutron Spectrum;

D O I：

10.1007/BF02672951

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

An improved method of measuring the absorbed gamma-ray dose rate using CaSO4 and SrSO4 type thermoluminescent detectors in models of iron shielding of a thermonuclear reactor is described. The reaction T(d, n)He-4 served as a neutron source. The method obtained makes it possible to determine the absorbed gamma-ray dose rate in shielding without using computed information and relying only on experimental data on the rates of nuclear reactions in threshold detectors.

引用

页码：222 / 228

页数：7

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