测量新乏核燃料后处理设施核安全装置中液体水平和密度的系统

IF 0.4 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY Atomic Energy Pub Date : 2024-08-21 DOI:10.1007/s10512-024-01108-5
A. A. Denisevich, A. G. Goryunov, S. N. Liventsov, G. V. Sumin, I. S. Nadezhdin
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引用次数: 0

摘要

文章介绍了一种用于测量核安全装置中液体的液位和密度的系统,该系统基于智能传感器和利用毛细管脉冲线对加工介质的多个点进行压差测量。该系统由探头、压差传感器和分离介质供应系统组成,可同时使用空气和液体作为分离介质。本文介绍了使用压缩空气分离介质对系统进行测试的结果。
本文章由计算机程序翻译,如有差异,请以英文原文为准。

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System for measuring the level and density of liquids in nuclear-safe devices for new spent nuclear fuel reprocessing facilities

The article presents a system for measuring the level and density of liquids in nuclear-safe devices, which is based on intelligent sensors and differential pressure measurements at several points of the process medium using capillary impulse lines. The presented system, which consists of a probe, differential pressure sensors, and a separating medium supply system, is operable when both air and liquid are used as a separating medium. The results of testing the system using a compressed air separating medium are presented.

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来源期刊
Atomic Energy
Atomic Energy 工程技术-核科学技术
CiteScore
1.00
自引率
20.00%
发文量
100
审稿时长
4-8 weeks
期刊介绍: Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.
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