Analysis of load energy feedback in pulsed coils power supply for the DIII-D tokamak

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

Fusion Engineering and Design Pub Date : 2025-04-02 DOI:10.1016/j.fusengdes.2025.115003

Qian Jiang , Ge Gao , Shusheng Wang , Zongjie Fu

{"title":"Analysis of load energy feedback in pulsed coils power supply for the DIII-D tokamak","authors":"Qian Jiang , Ge Gao , Shusheng Wang , Zongjie Fu","doi":"10.1016/j.fusengdes.2025.115003","DOIUrl":null,"url":null,"abstract":"<div><div>In response to the issue of power device damage in pulsed power supply system of DIII-D Tokamak device caused by the rise in DC bus voltage due to energy feedback from the superconducting load coil during physical experiments. This paper focused on the mechanism analysis of energy feedback from strongly magnetically coupled load coils. Initially, theoretical calculations are performed to assess the energy fed back from the load side to the DC side of the power supply during normal pulsed operation in the second or fourth quadrant. To ensure the continuous operation of normal pulses, an energy absorption circuit for the DC bus is designed, and the parameters of this circuit are carefully calculated. The proposed absorption circuit is capable of absorbing 100–150 kJ of energy feedback from the load coils during a 10s/10 min pulsed operation mode. Furthermore, a thyristor bypass circuit is designed to short-circuit the load coil within 3–5 ms in the event of an unexpected shutdown or termination of the experiment, thereby protecting the electrical equipment. Finally, the proposed solution is validated through simulation to ensure the power supply system can reliably handle the energy feedback from the load.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 115003"},"PeriodicalIF":1.9000,"publicationDate":"2025-04-02","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/S0920379625002030","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

In response to the issue of power device damage in pulsed power supply system of DIII-D Tokamak device caused by the rise in DC bus voltage due to energy feedback from the superconducting load coil during physical experiments. This paper focused on the mechanism analysis of energy feedback from strongly magnetically coupled load coils. Initially, theoretical calculations are performed to assess the energy fed back from the load side to the DC side of the power supply during normal pulsed operation in the second or fourth quadrant. To ensure the continuous operation of normal pulses, an energy absorption circuit for the DC bus is designed, and the parameters of this circuit are carefully calculated. The proposed absorption circuit is capable of absorbing 100–150 kJ of energy feedback from the load coils during a 10s/10 min pulsed operation mode. Furthermore, a thyristor bypass circuit is designed to short-circuit the load coil within 3–5 ms in the event of an unexpected shutdown or termination of the experiment, thereby protecting the electrical equipment. Finally, the proposed solution is validated through simulation to ensure the power supply system can reliably handle the energy feedback from the load.

查看原文本刊更多论文

求助全文

约1分钟内获得全文求助全文

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.