光纤光栅的流动特性及其在核热工实验中的潜在应用

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-10-25 DOI:10.3390/jne4040042
Harvey Oliver Plows, Jinfeng Li, Marcus Dahlfors, Marat Margulis
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引用次数: 0

摘要

随着核电在实现净零碳排放目标方面发挥的作用越来越大,对理解当前和未来反应堆概念核心的热水力现象的需求越来越大。为了满足这一需求,开发高分辨率的流动分析仪器变得越来越重要。在流体流动分析的背景下,一种未被充分利用和研究的仪器技术是基于光纤布拉格光栅(FBG)的传感器。该技术允许构建简单、微创的仪器,耐高温、高压和腐蚀,同时适用于测量各种流体性质,包括温度、压力、折射率、化学浓度、流速和空隙率,甚至在不透明介质中也是如此。此外,相关的FBG阵列已经开发出来,能够重建大相结构的3D图像,例如与阵列相互作用的段塞流中的气泡。目前一个显著未开发的应用,基于fbg的仪器因此显示出巨大的潜力,利用实验热工水力;扩展可用的流体表征和成像技术。因此,本文将概述当前基于fbg的流动表征技术,并系统回顾这些技术如何在核热工力学实验中得到应用。最后,将讨论如何在核研究中进一步发展和使用这些技术。
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Flow Characterisation Using Fibre Bragg Gratings and Their Potential Use in Nuclear Thermal Hydraulics Experiments
With the ever-increasing role that nuclear power is playing to meet the aim of net zero carbon emissions, there is an intensified demand for understanding the thermal hydraulic phenomena at the heart of current and future reactor concepts. In response to this demand, the development of high-resolution flow analysis instrumentation is of increased importance. One such under-utilised and under-researched instrumentation technology, in the context of fluid flow analysis, is fibre Bragg grating (FBG)-based sensors. This technology allows for the construction of simple, minimally invasive instruments that are resistant to high temperatures, high pressures and corrosion, while being adaptable to measure a wide range of fluid properties, including temperature, pressure, refractive index, chemical concentration, flow rate and void fraction—even in opaque media. Furthermore, concertinaing FBG arrays have been developed capable of reconstructing 3D images of large phase structures, such as bubbles in slug flow, that interact with the array. Currently a significantly under-explored application, FBG-based instrumentation thus shows great potential for utilisation in experimental thermal hydraulics; expanding the available flow characterisation and imaging technologies. Therefore, this paper will present an overview of current FBG-based flow characterisation technologies, alongside a systematic review of how these techniques have been utilised in nuclear thermal hydraulics experiments. Finally, a discussion will be presented regarding how these techniques can be further developed and used in nuclear research.
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来源期刊
CiteScore
1.30
自引率
0.00%
发文量
56
期刊介绍: The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.
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