23rd IAEA Fusion Energy Conference: summary of sessions EX/C and ICC

Hawryluk, R. J.

doi:10.1088/0029-5515/51/9/094005

Cited by 4 publications

(4 citation statements)

References 68 publications

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“…The offset rotation rate is about 1% of the Alfvén frequency, more than double the rotation needed for stable operation at high β above the no-wall kink limit in DIII-D [100] and JT-60U [101] (section 2.6). An important consequence is that the non-resonant field torque in a fusion plasma from high-n fields for ELM suppression [139] may not present a problem, but instead may generate a plasma rotation sufficient to benefit confinement and stability in a fusion reactor!…”

Section: Nonresonant External Perturbation-induced Toroidal Rotationmentioning

confidence: 99%

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Stabilization of the external kink and the resistive wall mode

Chu

Okabayashi

2010

Plasma Phys. Control. Fusion

200

294

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The pursuit of steady-state economic production of thermonuclear fusion energy has led to research on the stabilization of the external kink and the resistive wall mode. Advances in both experiment and theory, together with improvements in diagnostics, heating and feedback methods have led to substantial and steady progress in the understanding and stabilization of these instabilities. Many of the theory and experimental techniques and results that have been developed are useful not only for the stabilization of the resistive wall mode. They can also be used to improve the general performance of fusion confinement devices. The conceptual foundations and experimental results on the stabilization of the external kink and the resistive wall mode are reviewed.

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Section: Nonresonant External Perturbation-induced Toroidal Rotationmentioning

confidence: 99%

“…The in-vessel coils [139] for ELM control (figure 50) are proposed to be used for RWM and error field control.…”

Section: Itermentioning

confidence: 99%

Stabilization of the external kink and the resistive wall mode

Chu

Okabayashi

2010

Plasma Phys. Control. Fusion

200

294

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“…The new data reported in this paper remove that uncertainty by delaying the L-H transition to a time in the discharge with nearly stationary dW /dt and P OH , and repeating the experiment over a range of divertor recycling conditions. Preliminary analysis of the present dataset is presented in recent overview papers [21,22,23].…”

Section: Experiments On Nstxmentioning

confidence: 99%

Dependence of the L–H transition on X-point geometry and divertor recycling on NSTX

et al. 2013

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The edge electron (Te) and ion temperature (Ti) at the time of the L–H transition increase when the X-point radius (RX) is reduced to a high-triangularity shape while maintaining constant edge density. Consequently the L–H power threshold (PLH) is larger for the high-triangularity shape. This supports the prediction that a single-particle loss hole, whose properties are strongly linked to RX and Ti, influences the edge radial electric field (Er) and Er × B flow-shearing rate available for turbulence suppression. Simulations using XGC0, a full-f drift-kinetic neoclassical code, indicate that maintaining a constant Er × B flow-shearing rate does require a larger heat flux and edge Ti as RX decreases. NSTX also observes a decrease in PLH when the divertor recycling is decreased using lithium coatings. However, the edge Te and Ti at the L–H transition appear independent of the divertor recycling for a constant shape. XGC0 calculations demonstrate that more heat flux is needed to maintain the edge Ti and the Er × B flow-shearing rate as the contribution of divertor recycling to the overall neutral fuelling rate increases.

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“…Two routes were pursued to maximise chances of success and to explore complementary physics: baseline (high current route) and hybrid (high beta route), both leading to similar average neutron rate in the 2019-2020 campaigns though they had to overcome scenario specific challenges [14], with recent progress reported in [9] and summarised below. Although priority was given to developing sustained performance rather than to obtaining short pulses with very high fusion power, it is worth noting that peak neutron rates of 5.7 × 10 16 n s −1 were obtained in hybrid plasmas, matching DD neutrons records in TFTR [15], JET and JT-60U [16]. These plasmas are likely to provide the highest α power in DT, complementing dedicated studies for clear α effects (see sections 2.2 and 2.3).…”

Section: Scenarios For Sustained High Fusion Powermentioning

confidence: 86%

Overview of JET results for optimising ITER operation

et al. 2022

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The JET 2019-2020 scientific and technological programme exploited the results of years of concerted scientific and engineering work, including the ITER-like wall (ILW: Be wall and W divertor) installed in 2010, improved diagnostic capabilities now fully available, a major Neutral Beam Injection (NBI) upgrade providing record power in 2019-2020, and tested the technical & procedural preparation for safe operation with tritium. Research along three complementary axes yielded a wealth of new results. Firstly, the JET plasma programme delivered scenarios suitable for high fusion power and alpha particle physics in the coming D-T campaign (DTE2), with record sustained neutron rates, as well as plasmas for clarifying the impact of isotope mass on plasma core, edge and plasma-wall interactions, and for ITER pre-fusion power operation. The efficacy of the newly installed Shattered Pellet Injector for mitigating disruption forces and runaway electrons was demonstrated. Secondly, research on the consequences of long-term exposure to JET-ILW plasma was completed, with emphasis on wall damage and fuel retention, and with analyses of wall materials and dust particles that will help validate assumptions and codes for design & operation of ITER and DEMO. Thirdly, the nuclear technology programme aiming to deliver maximum technological return from operations in D, T and D-T benefited from the highest D-D neutron yield in years, securing results for validating radiation transport and activation codes, and nuclear data for ITER.

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23rd IAEA Fusion Energy Conference: summary of sessions EX/C and ICC

Cited by 4 publications

References 68 publications

Stabilization of the external kink and the resistive wall mode

Stabilization of the external kink and the resistive wall mode

Dependence of the L–H transition on X-point geometry and divertor recycling on NSTX

Overview of JET results for optimising ITER operation

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