基于气体电子倍增器(GEM)探测器的核聚变反应堆中子谱仪

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
M. Scholz , U. Wiącek , K. Drozdowicz , A. Jardin , U. Woźnicka , K. Król , A Kurowski , A. Kulińska , W. Dąbrowski , B. Łach , D. Mazon
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引用次数: 0

摘要

中子光谱法是测定核聚变堆堆芯等离子体中氘氚密度比和离子温度的一种重要诊断方法。以ITER为例,可以预见以下光谱技术:薄膜质子反冲(TPR)、钻石和飞行时间探测器。ITER的TPR光谱仪设计包括一个硅探测器系统,用于检测聚乙烯转化器中中子转化产生的质子。这种安排有其缺点,其中之一是硅对辐射损伤的抵抗力有限。因此,我们建议使用气体电子倍增器(GEM)型气体探测器,它应该比硅基探测器具有更好的电阻。介绍了一种基于GEM技术的TPR中子星光谱仪的概念和工作原理,即NS-GEM,用于未来的聚变等离子体光谱分析。讨论了探测器的几何形状及其基于数值计算的可行性研究。特别地,展示了NS-GEM演示器在IGN-14中子发生器上的第一次实验结果。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Neutron spectrometer based on a gas electron multiplier (GEM) detector for fusion reactors
Neutron spectrometry is an important diagnostic method that will be used to determine the deuterium to tritium density ratio and the ion temperature in the core plasma of fusion reactors. In the case of ITER, the following spectrometric techniques are foreseen: Thin-foil Proton Recoil (TPR), diamond and time-of-flight detectors. The TPR spectrometer design for ITER includes a system of silicon detectors for the detection of protons resulting from the conversion of neutrons in a polyethylene converter. This arrangement has its drawbacks, one of which is limited resistance of silicon to radiation damage. Therefore, we propose using a Gas Electron Multiplier (GEM) type gas detector, which should have better resistance than silicon-based detectors. The concept and operating principle of a TPR neutron spectrometer based on GEM technology, so-called NS-GEM and intended for future fusion plasma spectrometry applications, is presented. The geometry of the detector and its feasibility study based on numerical calculations are discussed. In particular, the first results of experiments with a NS-GEM demonstrator on the IGN-14 neutron generator are shown.
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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