Sai Tej Paruchuri , Ian Ward , Nicholas Rist , Vincent Graber , Hassan Al Khawaldeh , Zibo Wang , Eugenio Schuster , Andres Pajares , June-Woo Juhn
{"title":"Density regulation with disruption avoidance in next-generation tokamaks using a safe reinforcement learning-based controller","authors":"Sai Tej Paruchuri , Ian Ward , Nicholas Rist , Vincent Graber , Hassan Al Khawaldeh , Zibo Wang , Eugenio Schuster , Andres Pajares , June-Woo Juhn","doi":"10.1016/j.fusengdes.2025.115064","DOIUrl":null,"url":null,"abstract":"<div><div>Achieving high particle density is desirable in fusion reactors because of its direct correlation to the fusion power. However, operational limits constrain the maximum achievable particle density. Several density control algorithms have been designed to inject particles using gas puffing and pellet injection to track carefully selected safe targets. However, a controller unaware of these operational limits may modulate the particle densities beyond the safe limits during transients caused by changing operating conditions. Designing plasma control algorithms that recognize these operational limits and ensure that the particle density remains within the safe operational space is desirable. This work focuses on the safe regulation of deuterium–tritium (DT) particle density. Under the assumption of quasi-neutrality, the total plasma density can be related to the electron density, which is constrained by the well-known Greenwald limit. To regulate the DT density within the safe operational space defined by Greenwald limit, a novel safe reinforcement learning-based controller is developed in this work. Such control-design approach can be critical in designing learning-based safe plasma control algorithms for next-generation tokamaks. The effectiveness of the controller is demonstrated through nonlinear simulations conducted over multiple test cases.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115064"},"PeriodicalIF":1.9000,"publicationDate":"2025-04-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625002625","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
Achieving high particle density is desirable in fusion reactors because of its direct correlation to the fusion power. However, operational limits constrain the maximum achievable particle density. Several density control algorithms have been designed to inject particles using gas puffing and pellet injection to track carefully selected safe targets. However, a controller unaware of these operational limits may modulate the particle densities beyond the safe limits during transients caused by changing operating conditions. Designing plasma control algorithms that recognize these operational limits and ensure that the particle density remains within the safe operational space is desirable. This work focuses on the safe regulation of deuterium–tritium (DT) particle density. Under the assumption of quasi-neutrality, the total plasma density can be related to the electron density, which is constrained by the well-known Greenwald limit. To regulate the DT density within the safe operational space defined by Greenwald limit, a novel safe reinforcement learning-based controller is developed in this work. Such control-design approach can be critical in designing learning-based safe plasma control algorithms for next-generation tokamaks. The effectiveness of the controller is demonstrated through nonlinear simulations conducted over multiple test cases.
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.