A distributed real-time diagnostic and control network for the TCV tokamak based on the Data Distribution Service

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-08-05 DOI:10.1016/j.fusengdes.2025.115344

R. Masocco , A. Tenaglia , C. Galperti , D. Carnevale , S. Galeani , TCV Team , EUROfusion Tokamak Exploitation Team

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引用次数: 0

Abstract

A novel communication network is being implemented on the machines composing the Système de Contrôle Distribué (SCD) that form the real-time architecture of the Tokamak à Configuration Variable (TCV), exploiting the capabilities of the Data Distribution Service (DDS) middleware. This work presents a new DataSource for the MARTe2 framework that integrates the eProsima Fast DDS implementation. Its design is discussed, providing tools to configure the behavior of the DDS middleware, and its validation is performed by benchmarks on the SCD nodes hardware. The advantages of this work are twofold. First, the intention is to expand the capabilities of the SCD, which originally relies on a reflective memory that, although deterministic, requires specialized hardware and offers limited bandwidth and scalability. Secondly, integration of the DDS into the SCD enables more diagnostics to work in real time, expanding the experimental capabilities of the TCV device.

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基于数据分布服务的TCV托卡马克分布式实时诊断与控制网络

在构成托卡马克配置变量（TCV）的实时架构的系统 (SCD)的机器上实现了一种新的通信网络，利用了数据分布服务（DDS）中间件的功能。这项工作为MARTe2框架提供了一个新的数据源，该框架集成了eProsima快速DDS实现。讨论了它的设计，提供了配置DDS中间件行为的工具，并通过SCD节点硬件上的基准测试执行了它的验证。这项工作的好处是双重的。首先，目的是扩展SCD的功能，SCD最初依赖于反射内存，尽管反射内存是确定的，但需要专门的硬件，并且提供有限的带宽和可伸缩性。其次，将DDS集成到SCD中可以实时进行更多诊断，从而扩展了TCV设备的实验能力。

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.