开发高伽马和中子背景环境下的α射线可视化测量仪。

IF 0.8 4区 环境科学与生态学 Q4 ENVIRONMENTAL SCIENCES
Youichi Tsubota, Kenji Kobayashi, Tatsuya Ishii, Misaki Hirato, Satoshi Shioya, Takahiro Nakagawa
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引用次数: 0

摘要

为了可靠地检测和显示高γ/n-射线本底辐射环境中α-核素对防护服和物体表面的污染情况,我们开发了一种测量仪。勘测仪的特点是将一个半不透明的 ZnS:Ag 闪烁器直接安装在多阳极光电倍增管 (MA-PMT) 和放大电路上,确保所有通道的输出增益均衡。通过直接安装闪烁体,可抑制光在到达 MA-PMT 之前的扩散,将其集中在少数几个通道中,从而便于与本底辐射区分开来。这种设计还能清晰显示表面污染的形状。即使在超过 1 Sv/h 的高辐射环境中,原型测量仪的响应速度也能达到 2.1 × 107 cpm,且无 γ 射线响应。在高本底辐射的实际环境中,可以可靠地检测到约为表面污染密度极限 4 Bq/cm2 1/100 的污染。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Development of α-ray visualization survey meter in high gamma and neutron background environment.

A survey meter was developed to reliably detect and visualize surface contamination of suits and objects by α-nuclides in high γ/n-rays background radiation environment. The survey meter features a semi-opaque ZnS:Ag scintillator mounted directly onto a multi-anode photomultiplier tube (MA-PMT) and amplification circuits, ensuring output gain equalization for all channels. α-ray events induce localized light emission in thin-film scintillators. By directly mounting the scintillator, diffusion of light before reaching the MA-PMT is suppressed, concentrating it in just a few channels, thereby facilitating discrimination from background radiation. This design also enables clear visualization of the shape of surface contamination. The prototyped survey meter is capable of responding up to 2.1 × 107 cpm, with no γ-ray response even in high-radiation environments exceeding 1 Sv/h. In actual environments with high background radiation, contamination of ~1/100th of the surface contamination density limit of 4 Bq/cm2 could be reliably detected.

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来源期刊
Radiation protection dosimetry
Radiation protection dosimetry 环境科学-公共卫生、环境卫生与职业卫生
CiteScore
1.40
自引率
10.00%
发文量
223
审稿时长
6-12 weeks
期刊介绍: Radiation Protection Dosimetry covers all aspects of personal and environmental dosimetry and monitoring, for both ionising and non-ionising radiations. This includes biological aspects, physical concepts, biophysical dosimetry, external and internal personal dosimetry and monitoring, environmental and workplace monitoring, accident dosimetry, and dosimetry related to the protection of patients. Particular emphasis is placed on papers covering the fundamentals of dosimetry; units, radiation quantities and conversion factors. Papers covering archaeological dating are included only if the fundamental measurement method or technique, such as thermoluminescence, has direct application to personal dosimetry measurements. Papers covering the dosimetric aspects of radon or other naturally occurring radioactive materials and low level radiation are included. Animal experiments and ecological sample measurements are not included unless there is a significant relevant content reason.
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