M. Goniche
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View article: Design and analysis of a PAM launcher at 4.6 GHz for a new LHCD system on EAST
Design and analysis of a PAM launcher at 4.6 GHz for a new LHCD system on EAST Open
To improve the Current Drive (CD) capability in long-pulse (up to ∼1000 s) H-mode operation, it has been decided to develop a new Lower Hybrid Current Drive system at 4.6 GHz with an active cooling Passive Active Multijunction (PAM) launch…
View article: First lower hybrid current drive experiments on the WEST tokamak
First lower hybrid current drive experiments on the WEST tokamak Open
The first lower hybrid current drive experiments in the full tungsten WEST tokamak are reported. Good wave coupling is found at rather low plasma current (q95~4.3) and medium density (ne~3×1019m-3). Reflection coefficient is in agreement w…
View article: Tungsten accumulation during ion cyclotron resonance heating operation on WEST
Tungsten accumulation during ion cyclotron resonance heating operation on WEST Open
The observation of radiative collapses during ion cyclotron resonance heating (ICRH) operation on the full tungsten WEST tokamak constitutes a unique opportunity to get a quantitative balance of the sources and sinks in the core region of …
View article: The JET hybrid scenario in Deuterium, Tritium and Deuterium-Tritium
The JET hybrid scenario in Deuterium, Tritium and Deuterium-Tritium Open
The JET hybrid scenario has been developed from low plasma current carbon wall discharges to the record-breaking Deuterium-Tritium plasmas obtained in 2021 with the ITER-like Be/W wall. The development started in pure Deuterium with refine…
View article: First experimental results of the PAM LHCD launcher at 2.45 GHz on EAST
First experimental results of the PAM LHCD launcher at 2.45 GHz on EAST Open
This paper presents the first results of a passive active multijunction (PAM) launcher at 2.45 GHz during the lower hybrid current drive (LHCD) experiments on EAST. Good coupling performance with a power reflection coefficient ( RC ) ∼3% h…
View article: Separatrix parameters and core performances across the WEST L-mode database
Separatrix parameters and core performances across the WEST L-mode database Open
WEST database analysis shows a correlation of the recycled neutral source around the separatrix with core performances. This observation questions the causality chain between particle source and turbulent transport up to the core in L-mode…
View article: Developing high performance RF heating scenarios on the WEST tokamak
Developing high performance RF heating scenarios on the WEST tokamak Open
High power experiments, up to 9.2 MW with LHCD and ICRH, have been carried out in the full tungsten tokamak WEST. Quasi non inductive discharges have been achieved allowing to extend the plasma duration to 53 s with stationary conditions i…
View article: Characterizing W sources in the all-W wall, all-RF WEST tokamak environment<sup> <sup>*</sup> , <sup>**</sup> </sup>
Characterizing W sources in the all-W wall, all-RF WEST tokamak environment<sup> <sup>*</sup> , <sup>**</sup> </sup> Open
Experimental data, together with interpretive modeling tools, are examined to study trends in the tungsten (W) source in the all-W environment of the WEST tokamak, both from the divertor and from the main chamber. In particular, a poloidal…
View article: Improvement of lower hybrid current drive systems for high-power and long-pulse operation on EAST
Improvement of lower hybrid current drive systems for high-power and long-pulse operation on EAST Open
International audience
View article: Healing plasma current ramp-up by nitrogen seeding in the full tungsten environment of WEST
Healing plasma current ramp-up by nitrogen seeding in the full tungsten environment of WEST Open
Achieving a successful plasma current ramp-up in a full tungsten tokamak can be challenging due to the large core radiation (and resulting low core temperature) that can be faced with this heavy metallic impurity if its relative concentrat…
View article: WEST actively cooled load resilient ion cyclotron resonance heating system results
WEST actively cooled load resilient ion cyclotron resonance heating system results Open
Three identical new WEST ion cyclotron resonance heating (ICRH) antennas have been designed, assembled then commissioned on plasma from 2013 to 2019. The WEST ICRH system is both load-resilient and compatible with long-pulse operations. Th…
View article: Formation of the radial electric field profile in the WEST tokamak
Formation of the radial electric field profile in the WEST tokamak Open
Sheared flows are known to reduce turbulent transport by decreasing the correlation length and/or intensity of turbulent structures. The transport barrier that takes place at the edge during improved regimes such as H mode, corresponds to …
View article: The geometry of the ICRF-induced wave–SOL interaction. A multi-machine experimental review in view of the ITER operation
The geometry of the ICRF-induced wave–SOL interaction. A multi-machine experimental review in view of the ITER operation Open
As part of ITPA-Integrated Operational Scenario activities, this contribution reviews recent experimental characterizations of radio-frequency (RF)-induced scrape-off layer (SOL) modifications of various tokamaks worldwide and of the LArge…
View article: Confinement properties in the large aspect ratio, full tungsten environment of the WEST tokamak
Confinement properties in the large aspect ratio, full tungsten environment of the WEST tokamak Open
WEST is a metallic tokamak operating in L mode since December 2016. Its specificities are an aspect ratio value of 5-6 and the inner wall covered with tungsten tiles plus ITER like PFU on lower divertor. Its plasmas are dominantly electron…
View article: WEST actively cooled load resilient ion cyclotron resonance heating system results
WEST actively cooled load resilient ion cyclotron resonance heating system results Open
Three identical new WEST ion cyclotron resonance heating (ICRH) antennas have been designed, assembled then commissioned on plasma from 2013 to 2019. The WEST ICRH system is both load-resilient and compatible with long-pulse operations. Th…
View article: HOW NITROGEN SEEDING SECURIZES PLASMA RAMP-UP IN THE METALLIC ENVIRONMENT OF WEST
HOW NITROGEN SEEDING SECURIZES PLASMA RAMP-UP IN THE METALLIC ENVIRONMENT OF WEST Open
International audience
View article: Operating near the L-H power threshold in WEST full tungsten environment
Operating near the L-H power threshold in WEST full tungsten environment Open
International audience
View article: Collisional transport and poloidal asymmetry distribution of impurities in tokamak plasmas, with application to WEST
Collisional transport and poloidal asymmetry distribution of impurities in tokamak plasmas, with application to WEST Open
International audience
View article: The geometry of ICRF - Induced wave-SOL interaction
The geometry of ICRF - Induced wave-SOL interaction Open
As part of ITPA-IOS activities, this contribution reviews recent experimental characterization of Radio-Frequency
(RF)-induced Scrape-Off Layer (SOL) modifications on various tokamaks worldwide and on the LArge Plasma Device
(LAPD) at UC…
View article: Investigations of LHW-plasma coupling and current drive at high density related to H-mode experiments in EAST
Investigations of LHW-plasma coupling and current drive at high density related to H-mode experiments in EAST Open
Two important issues in achieving lower hybrid current drive (LHCD) high confinement plasma in EAST are to improve lower hybrid wave (LHW)-plasma coupling and to drive the plasma current at a high density. Studies in different configuratio…
View article: Coupling properties of the LHCD launchers in the WEST experiments
Coupling properties of the LHCD launchers in the WEST experiments Open
The aim of WEST [1] [2] is to master long pulses (> 30s and up to 1000s) and submit ITER like tungsten divertor tiles to power fluxes of 10 MW/m2. To reach these goals, the Tore Supra Lower Hybrid Current Drive system (LHCD) constituted by…
View article: First lower hybrid current drive experiments on the WEST tokamak
First lower hybrid current drive experiments on the WEST tokamak Open
The first lower hybrid current drive experiments in the full tungsten WEST tokamak are reported. Good wave coupling is found at rather low plasma current (q95∼4.3) and medium density (ne∼3×1019m-3). Reflection coefficient is in agreement w…
View article: First application of Ion Cyclotron resonant frequency waves on WEST plasma scenarios
First application of Ion Cyclotron resonant frequency waves on WEST plasma scenarios Open
In 2018, Ion Cyclotron Resonant Frequency (ICRF) waves were for the first time applied to the WEST plasma scenarios. In ICRF-only plasmas at medium density, or on top of a low level of Lower Hybrid (LH) power, the coupled ICRF power increa…
View article: Comparative modeling of lower hybrid wave coupling with 2.45 GHz and 4.6 GHz launchers on EAST
Comparative modeling of lower hybrid wave coupling with 2.45 GHz and 4.6 GHz launchers on EAST Open
Comparative modeling of the coupling properties and the power spectra with different plasma densities and different phasing were performed for 2.45 GHz and 4.6 GHz waves respectively by using the ALOHA code. The modeling results show that …
View article: ICRH coupling optimization and impurity behavior in EAST and WEST
ICRH coupling optimization and impurity behavior in EAST and WEST Open
This study compares experimental observations on the two challenges of Ion Cyclotron Resonance Heating (ICRH), namely the coupling of waves to the plasma and the enhanced impurity sputtering in EAST and WEST medium size tokamaks.In WEST, L…
View article: Progress of physics understanding for long pulse high-performance plasmas on EAST towards the steady-state operation of ITER and CFETR
Progress of physics understanding for long pulse high-performance plasmas on EAST towards the steady-state operation of ITER and CFETR Open
Recently, the first ever 100 s long, steady-state H-mode discharge with good control of impurities, core and edge MHD stabilities, and heat exhaust was demonstrated in the Experimental Advanced Superconducting Tokamak (EAST) using the ITER…
View article: Sub-divertor fuel isotopic content detection limit for JET and its impact on ICRF core heating and DTE2 operation
Sub-divertor fuel isotopic content detection limit for JET and its impact on ICRF core heating and DTE2 operation Open
The ability to detect and control fuel isotopic content down to a 1% concentration level is greatly important for the upcoming JET DTE2 campaign, as well as its associated TT and DD phases. A reduction of H minority concentration even from…
View article: Ramping up RF power and increasing pulse length in the full tungsten environment of WEST
Ramping up RF power and increasing pulse length in the full tungsten environment of WEST Open
International audience