Operation and remote collaboration tools in view of the ITER neutral beam test facility experimental campaigns

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

Fusion Engineering and Design Pub Date : 2025-04-28 DOI:10.1016/j.fusengdes.2025.115027

Nuno Cruz , Alastair Shepherd , Gabriele Manduchi , Cesare Taliercio , Paolo Barbato , Rita Delogu , Gianluigi Serianni , Andrea Rigoni , Luca Trevisan , Adriano Luchetta

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引用次数: 0

Abstract

The ITER Neutral Beam Test Facility (NBTF) serves as a crucial testing ground for the development and validation of neutral beam injection systems essential for ITER’s fusion power plant. For this purpose two experimental campaigns in the two prototypes (SPIDER and MITICA) are conducted within the NBTF.

Collaborative efforts at the NBTF, involving scientists from different institutions across Europe, India and Japan, emphasize the importance of data sharing and advanced computing infrastructures. Common computing platforms facilitate analysis of scientific data, aiding informed decision-making. Remote collaboration tools play a crucial role in fostering communication among global experts. The involvement of EUROfusion and ITER experts in strict collaboration accelerates ITER’s neutral beam heating and diagnostic systems development. Moreover, remote participation, data visualization, and efficient operation tools are essential for enhancing accessibility and collaboration in scientific research. These tools enable researchers to remotely access and control experimental facilities, visualize data in real-time, and collaborate with colleagues worldwide.

This paper presents the design and implementation of operation tools based on EPICS and MDSplus, developed using Grafana, Python, and NodeJS, to enhance remote participation, data visualization, plant operation and collaboration in fusion experiments. A key improvement in SPIDER’s pulse repetition rate, now reaching 300 s, was achieved through pre-approved pulses and automatic repetition, significantly increasing the average daily pulses. By using ITER CODAC standards and open-source tools like PostgreSQL, Redis, Grafana, MDSplus, and EPICS, we have optimized both operations and remote collaborations, improving security and efficiency in real-time trend visualization, automating experimental setup verification, optimizing experimental time and performance using real-time pulse sequence reconfiguration.

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针对ITER中性束流测试设施实验活动的操作和远程协作工具

ITER中性束试验设施（NBTF）是ITER核聚变发电厂必不可少的中性束注入系统的开发和验证的关键试验场。为此目的，在NBTF的两个原型（SPIDER和MITICA）中进行了两个实验活动。来自欧洲、印度和日本不同机构的科学家参与了NBTF的合作努力，强调了数据共享和先进计算基础设施的重要性。通用计算平台促进了科学数据的分析，有助于明智的决策。远程协作工具在促进全球专家之间的沟通方面发挥着至关重要的作用。欧洲核聚变和ITER专家的严格合作加速了ITER中性束加热和诊断系统的发展。此外，远程参与、数据可视化和高效的操作工具对于提高科学研究的可及性和协作性至关重要。这些工具使研究人员能够远程访问和控制实验设施，实时可视化数据，并与世界各地的同事合作。本文介绍了基于EPICS和MDSplus的操作工具的设计和实现，使用Grafana、Python和NodeJS开发，以增强融合实验中的远程参与、数据可视化、工厂操作和协作。通过预先批准的脉冲和自动重复，大大提高了SPIDER的脉冲重复率，目前达到300秒。通过使用ITER CODAC标准和开源工具（如PostgreSQL， Redis, Grafana， MDSplus和EPICS），我们优化了操作和远程协作，提高了实时趋势可视化的安全性和效率，自动化实验设置验证，优化实验时间和性能使用实时脉冲序列重构。

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.