Results 1 to 10 of about 1,193 (70)

Electron cyclotron heating assisted start-up experiments in J-TEXT [PDF]

EPJ Web of Conferences, 2023
Electron cyclotron heating (ECH) breakdown and burn-through assist has been adopted to make the ITER start-up, which uses a low toroidal electric field of about 0.3 V/m, more robust.
Zhang Junli, de Vries Peter C, Nagasaki Kazunobu, Xia Donghui, Jiang Wei, Yang Zhoujun, Cheng Zhifeng, Xu Xin, Wang Zhijiang, Wang Nengchao, Gao Li, Ding Yonghua, Chen Zhipeng, Chen Zhongyong, Pan Yuan   +14 more
doaj   +1 more source

The development of 1 MW ECRH system on J-TEXT [PDF]

EPJ Web of Conferences, 2023
A 1 MW electron cyclotron resonance heating system has been designed and developed for J-TEXT tokamak not only to enhance the total heating power but also to provide another possible way to control the plasma parameters.
Chen Xixuan, Xia Donghui, Zhang Junli, Wang Zhijiang, Pan Yuan   +4 more
doaj   +1 more source

Infrared detection of tungsten cracking on actively cooled ITER-like component during high power experiment in WEST

Nuclear Materials and Energy, 2023
The consequences of tungsten (W) damaging processes, such as cracking and melting, on divertor lifetime and plasma operation are high priority issues for ITER.
Q. Tichit, A. Durif, J. Gaspar, Y. Anquetin, Y. Corre, M. Diez, L. Dubus, M. Firdaouss, J. Gerardin, A. Grosjean, J.P. Gunn, K. Krieger, M. Missirlian, S. Ratynskaia, P. Reilhac, M. Richou, F. Rigollet   +16 more
doaj   +1 more source

Very high-resolution infrared imagery of misaligned tungsten monoblock edge heating in the WEST tokamak

Nuclear Materials and Energy, 2021
Fourteen ITER-like plasma-facing units (PFUs) made of bulk tungsten were installed in the WEST tokamak divertor. Five of which were misaligned with their poloidal leading edges (LEs) exposed to the plasma heat flux: two sharp-edge PFUs and three ...
A. Grosjean, Y. Corre, J. Gaspar, J.P. Gunn, S. Carpentier, X. Courtois, R. Dejarnac, E. Delmas, G. De Temmerman, M. Diez, L. Dubus, L. Dupont, F. Escourbiac, M. Firdaouss, J. Gerardin, M. Houry, R. Pitts, C. Pocheau, E. Tsitrone   +18 more
doaj   +1 more source

Testing of ITER-grade plasma facing units in the WEST tokamak: Progress in understanding heat loading and damage mechanisms

Nuclear Materials and Energy, 2023
Assessing the performance of the ITER design for the tungsten (W) divertor Plasma Facing Units (PFUs) in a tokamak environment is a high priority issue to ensure efficient plasma operation.
Y. Corre, M-H. Aumeunier, A. Durif, J. Gaspar, K. Krieger, T. Loewenhoff, M. Richou, S. Ratynskaia, Q. Tichit, Y. Anquetin, R. Dejarnac, M. Diez, L. Dubus, M. Firdaouss, J. Gerardin, A.. Grosjean, J.P. Gunn, T. Loarer, P. Maget, C. Martin, K. Paschalidis, E. Tsitrone, M. Wirtz   +22 more
doaj   +1 more source

Plasma exposure of a pre-damaged ITER-like plasma facing unit in the WEST tokamak: in-situ and post-mortem measurements

Nuclear Materials and Energy, 2023
The consequences of tungsten (W) cracking on divertor lifetime and plasma operation are high priority issues for ITER. One actively cooled ITER-like plasma facing unit (PFU) has been pre-damaged in a High Heat Flux (HHF) facility before its installation ...
Yann Corre, Torsten Loewenhoff, Marianne Richou, Sebastijan Brezinsek, Jan Coenen, Renaud Dejarnac, Mathilde Diez, Nicolas Fedorczak, Mehdi Firdaouss, Jonathan Gaspar, Alex Grosjean, James-Paul Gunn, Thierry Loarer, Céline Martin, Gerald Pintsuk, Pierre Reilhac, Quentin Tichit, Emmanuelle Tsitrone, Marius Wirtz, the WEST team   +19 more
doaj   +1 more source

Project Design of a Pulsed D-D Fusion Neutron Source Based on Field Reversed Configuration

中国工程科学, 2022
The fusion neutron source is of great significance for conducting material testing for future fusion reactors, as it can genuinely reflect the change of material properties under fusion neutron irradiation.
Pan Yuan, Wang Zhijiang , Wu Songtao , Zhang Ming , Chen Zhipeng , Rao Bo , Zhu Ping, Yang Yong, Ding Yonghua   +8 more
doaj   +1 more source

OEDGE modeling of far-SOL tungsten impurity sources and screening in WEST

Nuclear Materials and Energy, 2022
The plasma background and impurity transport in the scrape-off layer (SOL) of the WEST tokamak are modeled for three discharges over a Psep power scan ranging between 1.5 and 2.35 MW. An extended modeling grid is used to investigate far-SOL sourcing from
J.B. Maeker, J.H. Nichols, D.C. Donovan, A. Grosjean, J. Gunn, N. Fedorczak, C. Guillemaut, C.C. Klepper, E.A. Unterberg, D.C. Easley, WEST Team   +10 more
doaj   +1 more source

Validation of the plasma-wall self-organization model for density limit in ECRH-assisted start-up of Ohmic discharges on J-TEXT

Nuclear Fusion, 2023
A recently developed plasma-wall self-organization model (Escande et al 2022 Nucl. Fusion 62 026001) predicts a significantly enhanced density limit, which may be attainable in tokamaks with ECRH-assisted Ohmic start-up and sufficiently high initial ...
Jiaxing Liu, Ping Zhu, Dominique Franck Escande, Junli Zhang, Donghui Xia, Yuhan Wang, Jiaming Wang, Qinghu Yang, Jiangang Fang, Xiaoqing Zhang, Li Gao, Zhifeng Cheng, Zhipeng Chen, Zhoujun Yang, Zhongyong Chen, Yonghua Ding, Yuan Pan, the J-TEXT Team   +17 more
doaj   +1 more source

IDP-PGFE: an interpretable disruption predictor based on physics-guided feature extraction

Nuclear Fusion, 2023
Disruption prediction has made rapid progress in recent years, especially in machine learning (ML)-based methods. If a disruption prediction model can be interpreted, it can tell why certain samples are classified as disruption precursors. This allows us
C. Shen, W. Zheng, Y. Ding, X. Ai, F. Xue, Y. Zhong, N. Wang, L. Gao, Z. Chen, Z. Yang, Z. Chen, Y. Pan, J-TEXT team   +12 more
doaj   +1 more source