Real-time estimation and control of divertor surface heat flux on the DIII-D tokamak-Reference-Cited by-同舟云学术

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Real-time estimation and control of divertor surface heat flux on the DIII-D tokamak

Published:2021-10 Issue: Volume:171 Page:112560
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Anand H.^ORCID,Eldon D.,Humphreys D.^ORCID,Hyatt A.^ORCID,Sammuli B.,Welander A.,Barr J.,Scotti F.,Boedo J.

Funder

Office of Science

Fusion Energy Sciences

U.S. Department of Energy

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference23 articles.

1. Summary of the international workshop on magnetic fusion energy (MFE) roadmapping in the ITER Era; 7–10 September 2011, Princeton, NJ, USA;Neilson;Nucl. Fusion,2012

2. DEMO design activity in Europe: progress and updates;Federici;Fusion Eng. Des.,2018

3. Overview of the present progress and activities on the CFETR;Wan;Nucl. Fusion,2017

4. The JET real-time plasma-wall load monitoring system;Valcárcel;Fusion Eng. Des.,2014

5. Implementing a finite-state off-normal and fault response system for disruption avoidance in tokamaks;Eidietis;Nucl. Fusion,2018

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Virtual Tokamak for Test and Development of Plasma Control Applied to NSTX-U;IEEE Transactions on Plasma Science;2024

2. Vertical control of DIII-D discharges with strong negative triangularity;Plasma Physics and Controlled Fusion;2023-03-03

3. Benchmark of a self-consistent dynamic 1D divertor model DIV1D using the 2D SOLPS-ITER code;Plasma Physics and Controlled Fusion;2022-11-11

4. Concepts and challenges in the design of a tokamak plasma control system. ITER PCS for First Plasma and beyond;2022 IEEE Conference on Control Technology and Applications (CCTA);2022-08-23

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