Design of a distributed data acquisition system for the ITER's neutral beam

Abstract

The International Thermonuclear Experimental Reactor (ITER) is a groundbreaking interna- tional collaboration aimed at developing fusion energy as a clean, safe, and virtually limitless source of power that brings together scientists, engineers, and experts from 35 countries to con- struct and operate the world’s largest experimental fusion reactor. Through the fusion of hy- drogen isotopes, ITER seeks to replicate the process that powers the sun and stars, harnessing the immense energy released to generate electricity. With its ambitious goals and cutting-edge technology, ITER represents a significant milestone in the pursuit of sustainable and abundant energy for the future. As part of the ITER project, the development of several systems of plasma heating is needed to achieve fusion conditions in order to reach plasma ignition. One of such heating systems is the Heating Neutral Beam (HNB), which is designed to inject a energetic beam of neutral atoms into the plasma and heat the fusion plasma by coulomb collisions of such with the plasma. This system requires of several components such as power supplies, cryopumps and cooling components working together in order to achieve a controlled and safe operation of the HNB. It also needs to work coordinated with the experimental control with high availability. The neutral beam control system is, therefore, responsible for the correct and safe operation of the two HNB units installed at ITER. The project presents an overview of the instrumentation and control system currently being developed for the Neutral Beam units and presents the development and design of a remote distributed data acquisition system prototype for the Neutral Beam instrumentation and control system. The performance of the prototype will be measured and evaluated to determine if such solution is fit for ITER requirements and can therefore be implemented into the Neutral Beam control system and other control systems within the reactor components. This project was developed under the Traineeship program by the European Joint Undertaking for ITER and the Development of Fusion Energy, Fusion For Energy (F4E). This report presents the work the author performed during such contract and under the guidance of the program’s supervisors