Improved confinement with reversed magnetic shear in TFTR

Levinton, F.M.; Batha, S.H.; Zarnstorff, M. C.

doi:10.2172/93983

Cited by 5 publications

(6 citation statements)

References 3 publications

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“…In comparable experiments performed without LH power, no signifi cant change in temperature and current density profi les was seen. A possible interpretation of this result is that, operating at ITER-relevant plasma densities and with suffi ciently high peripheral plasma temperature, the launched LH waves penetrate and drive current in the plasma core, which, in turn, produces an improvement in plasma confi nement through the generation of a low magnetic shear 32 . Using the LH star code, which is described by Cesario et al 11,12 , the PI-induced spectral broadening has been calculated and used to determine the LH deposition in the plasma.…”

Section: Resultsmentioning

confidence: 99%

Current drive at plasma densities required for thermonuclear reactors

Cesario¹,

Amicucci²,

Cardinali³

et al. 2010

Nat Commun

137

140

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Progress in thermonuclear fusion energy research based on deuterium plasmas magnetically confi ned in toroidal tokamak devices requires the development of effi cient current drive methods. Previous experiments have shown that plasma current can be driven effectively by externally launched radio frequency power coupled to lower hybrid plasma waves. However, at the high plasma densities required for fusion power plants, the coupled radio frequency power does not penetrate into the plasma core, possibly because of strong wave interactions with the plasma edge. Here we show experiments performed on FTU (Frascati Tokamak Upgrade) based on theoretical predictions that nonlinear interactions diminish when the peripheral plasma electron temperature is high, allowing signifi cant wave penetration at high density. The results show that the coupled radio frequency power can penetrate into high-density plasmas due to weaker plasma edge effects, thus extending the effective range of lower hybrid current drive towards the domain relevant for fusion reactors.

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Section: Resultsmentioning

confidence: 99%

Current drive at plasma densities required for thermonuclear reactors

Cesario¹,

Amicucci²,

Cardinali³

et al. 2010

Nat Commun

137

140

View full text Add to dashboard Cite

show abstract

“…[86]. Here, q eff ~0.8q 95 . High  N regime is characterized by relatively higher li and high  p regime is characterized by a relatively lower li below the sawtooth boundary [87].…”

Section: Current Profile Control Of High Bootstrap Current Fraction Pmentioning

confidence: 99%

“…Since the bootstrap current is a hollow current profile and has 1/B p dependence, it is easier to obtain a higher bootstrap current fraction with a hollow current profile. Since then, many works have been done for optimization of the reversed shear scenario in both theory [93,94] and experiments in TFTR [95], DIII-D [96], and JT-60U [97]. To achieve a hollow current profile, a step-up scenario of P NB power during the current ramp-up (dIp/dt~0.5MA/s) is the key aspect to obtain a high electron temperature and to enhance the skin current effect.…”

Section: Negative Shear and Current Hole Regimesmentioning

confidence: 99%

A Review of Fusion and Tokamak Research Towards Steady-State Operation: A JAEA Contribution

Kikuchi

2010

Energies

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Providing a historical overview of 50 years of fusion research, a review of the fundamentals and concepts of fusion and research efforts towards the implementation of a steady state tokamak reactor is presented. In 1990, a steady-state tokamak reactor (SSTR) best utilizing the bootstrap current was developed. Since then, significant efforts have been made in major tokamaks, including JT-60U, exploring advanced regimes relevant to the steady state operation of tokamaks. In this paper, the fundamentals of fusion and plasma confinement, and the concepts and research on current drive and MHD stability of advanced tokamaks towards realization of a steady-state tokamak reactor are reviewed, with an emphasis on the contributions of the JAEA. Finally, a view of fusion energy utilization in the 21st century is introduced.

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“…Results from the DIII-D [56] and TFTR [57] tokamaks have demonstrated that a mode or modes of improved core confinement can by induced in discharges with reversed magnetic shear equilibria. Discovered independently, these modes are termed "Negative Central Shear" or NCS-mode (DIII-D) and "Enhanced Reverse Shear" or ERS-mode (TFTR).…”

Section: Ncs/ers Modementioning

confidence: 99%

Lithium pellet injection experiments on the Alcator C-Mod tokamak

Garnier

1996

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Improved confinement with reversed magnetic shear in TFTR

Cited by 5 publications

References 3 publications

Current drive at plasma densities required for thermonuclear reactors

Current drive at plasma densities required for thermonuclear reactors

A Review of Fusion and Tokamak Research Towards Steady-State Operation: A JAEA Contribution

Lithium pellet injection experiments on the Alcator C-Mod tokamak

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