利用嵌入式热测量和神经网络识别双衰减长度(λqt)热通量沉积形状

IF 2.3 2区 物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Y. Anquetin , J. Gaspar , Y. Corre , JL. Gardarein , J. Gerardin , P. Malard , F. Rigollet , Q. Tichit , E. Tsitrone , the WEST team , the EUROfusion Tokamak Exploitation team
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引用次数: 0

摘要

估算托卡马克装置中的热通量密度分布图是一个非常重要的研究课题,不仅可以用于边缘等离子体物理目的,还能确保机器的安全。在径向方向上,热通量呈现指数衰减,分布在面向等离子体的部件中的热传感器可以捕捉到这种衰减。基于光纤布拉格光栅技术的径向分布式热传感器已嵌入 WEST 下部分流器,用于研究等离子体运行期间的热通量沉积曲线。嵌入式测量结果与三维有限元模型之间的比较显示,在衰减长度约为 30 至 50 毫米的较宽热通量顶部,存在一个较小的衰减长度(5 - 10 毫米)。为了从稳定状态下的嵌入式温度测量值预测描述沉积热通量的不同参数值,我们开发了一种使用神经网络的工具。使用该工具对在 WEST 进行的 250 多个附带分流器配置的 L 模式脉冲实验数据库进行了分析,结果表明沉积热通量跨度很大,最大热通量从 1 到 9 兆瓦/平方米不等,衰减长度从 5 到 50 毫米不等。将预测的热通量参数值与宏观等离子体参数进行比较后发现,随着分流器功率负荷(Pdiv)的增加,会出现窄分量,其阈值取决于等离子体电流(IP)。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Identification of a double decay length (λqt) heat flux deposition shape with embedded thermal measurement and neural network
The estimation of the heat flux density distribution profiles in tokamak devices is a very important research topic for edge plasma physics purposes and also to ensure the safety of the machine. In the radial direction, the heat flux exhibits an exponential decay that could be captured by thermal sensors distributed in the plasma facing components. Radially distributed thermal sensors based on Fiber Bragg grating technology have been embedded in the WEST lower divertor to study the heat flux deposition profiles during plasma operation. The comparison between embedded measurements and a 3D finite element model shows a small decay length (5 – 10 mm) on top of a wider heat flux with a decay length around 30 to 50 mm. A tool using neural network has been developed in order to predict the values of the different parameters describing the deposited heat flux from embedded temperature measurements in steady state. A large span of deposited heat fluxes with maximum heat flux ranging from 1 to 9 MW/m2 and decay length from 5 to 50 mm were characterized using this tool over a database of more than 250 experimental L-mode pulses performed in WEST in attached divertor configuration. The comparison of the predicted heat flux parameters values with macroscopic plasma parameters have revealed the appearance of the narrow component with the increase of the divertor power load (Pdiv) with a threshold dependant of the plasma current (IP).
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来源期刊
Nuclear Materials and Energy
Nuclear Materials and Energy Materials Science-Materials Science (miscellaneous)
CiteScore
3.70
自引率
15.40%
发文量
175
审稿时长
20 weeks
期刊介绍: The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.
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