Development of a PXIe-based data acquisition and control system for hydrogen pellet injection system

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2024-08-31 DOI:10.1016/j.fusengdes.2024.114641

M. Banaudha , J. Mishra , P. Panchal , S. Mukherjee , P. Nayak , V. Gupta , H. Agravat , R. Gangradey

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引用次数: 0

Abstract

A data acquisition and control (DAC) system has been developed for the solid hydrogen pellet injection system. This injector is a gas gun type injector, where solid hydrogen pellet ice is formed using a closed cycle cryocooler, and high-pressure helium gas or a pneumatic punch is used to dislodge the pellet. The DAC system is based on National Instrument's embedded controller NI PXIe-8133, along with associated I/O DAC cards and the LabVIEW application. A graphical user interface (GUI) developed using LabVIEW software allows users to remotely control the pellet formation and injection process. The data is stored locally on a desktop computer or in cloud storage for further analysis. The images of the injected pellet were obtained by using a Phantom V-1210 high-speed camera at 100-Killo FPS, which reveals the size and speed of the pellet. The developed DAC system provides the flexibility needed to operate the injector remotely during the plasma discharge in a tokamak environment. The injector setup system has been successfully tested in a test bench operation, and it will be integrated with the ADITYA-U tokamak.

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为氢粒喷射系统开发基于 PXIe 的数据采集和控制系统

为固体氢丸喷射系统开发了一个数据采集和控制系统（DAC）。该注射器为气枪式注射器，使用封闭循环低温冷却器形成固态氢丸冰，并使用高压氦气或气动冲头将氢丸冲出。DAC 系统基于美国国家仪器公司的嵌入式控制器 NI PXIe-8133，以及相关的 I/O DAC 卡和 LabVIEW 应用程序。使用 LabVIEW 软件开发的图形用户界面 (GUI) 允许用户远程控制颗粒形成和注射过程。数据存储在本地台式电脑或云存储中，以便进一步分析。通过使用 Phantom V-1210 高速相机以 100-Killo FPS 的速度获取注射颗粒的图像，从而显示颗粒的大小和速度。开发的 DAC 系统提供了在托卡马克环境中等离子体放电期间远程操作注入器所需的灵活性。喷射器设置系统已成功通过试验台测试，并将与 ADITYA-U 托卡马克集成。

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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来源期刊

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.