A channel for neutron flux measurement

被引：0
|
作者：
Chuklyaev, S.V. [1 ]
Pepyolyshev, Yu.N. [1 ]
Artem'ev, V.A. [1 ]
机构：
[1] Inst. of Materials Technol., Lytkarino, Moscow oblast, 140083, Russia
来源：
Pribory i Tekhnika Eksperimenta | 2002年 / 45卷 / 02期
关键词：
Control systems - Design - Fission products - Ionization chambers - Neutron detectors - Performance;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
The design principles of a channel for measuring fluxes of thermal neutrons in a nuclear-reactor control and protection system are considered. The channel consists of a fission chamber, a set of boron-containing gas-filled ionization chambers, and an electronic unit that ensures a counting rate of fission pulses of up to 1 × 106 s-1. It is shown that the widest linear range is achieved in channels equipped with a fission chamber and a gas-filled ionization chamber with electrodes coated with natural boron. The channel allows for measurements of the thermal-neutron flux density in a range of 0.5 to 5 × 1011 cm-2 s-1.
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页码：21 / 25
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