LiWALL FUSION — THE NEW CONCEPT OF MAGNETIC FUSION

Zakharov, L.E.

doi:10.21517/0202-3822-2011-34-1-29-38

Cited by 6 publications

(5 citation statements)

References 4 publications

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“…Because of the overall complexity of disruptions, the key to plasma stability control is in simplification of the plasma regime without sacrificing performance. The practical approach for solving the disruption problem is in development and implementation of the LiWall Fusion regime, 36 with a simpler core physics than in present tokamaks, the best possible in confinement and stability (no sawteeth, edge localized modes, density limit), with neutral beam injection controlled plasma, and stationary plasma-wall interactions. But this is a separate important topic broader than the disruptions.…”

Section: Discussionmentioning

confidence: 99%

Understanding disruptions in tokamaks

et al. 2012

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This paper describes progress achieved since 2007 in understanding disruptions in tokamaks, when the effect of plasma current sharing with the wall was introduced into theory. As a result, the toroidal asymmetry of the plasma current measurements during vertical disruption event (VDE) on the Joint European Torus was explained. A new kind of plasma equilibria and mode coupling was introduced into theory, which can explain the duration of the external kink 1/1 mode during VDE. The paper presents first results of numerical simulations using a free boundary plasma model, relevant to disruptions.

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Section: Discussionmentioning

confidence: 99%

Understanding disruptions in tokamaks

et al. 2012

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“…In 2006 the notion of 'the best confinement regime' with energy confinement determined by particle diffusion, rather than by (always anomalously high) thermal conduction, was formulated. Accordingly, in this regime the NBI is sufficient to fuel and maintain a high performance plasma [13,14]. As an application, a burning plasma regime for a 100 MW DEMO device was calculated [15].…”

Section: Nuclear Fusionmentioning

confidence: 99%

“…Four of them have the same input parameters as in table 1 with R ecycling = 0.5 and three cases have P NBI = 5 MW. The plasma profiles for table 3 are shown in figure E1 (cases 10-12) and figure F1 (cases [13][14][15].…”

Section: Overview Of Demonstration Astra Transport Runsmentioning

confidence: 99%

On a burning plasma low recycling regime with P _DT = 23–26 MW, Q _DT = 5–7 in a JET-like tokamak

Zakharov

2019

Nucl. Fusion

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The recent invention of a continuously flowing liquid lithium system, called 24/7-FLiLi, opens the opportunity to design a plasma pumping divertor which can significantly suppress plasma edge cooling by recycling. The paper describes the expected performance of deuterium–tritium burning plasma with low recycling using a tokamak of JET size, magnetic field and plasma current as an example. So far, only the technological aspects of flowing lithium have been tested on the HT-7 and EAST tokamaks (ASIPP, Hefei, China) with no attempts to create the low recycling regime. The compatibility of 24/7-FLiLi with tokamak plasma was confirmed and some mistakes in the design were revealed, thus, requiring another fabrication approach. Now, with the proper design of the Li system, recycling as low as 0.5 seems to be achievable. The suppression of plasma cooling by recycling in combination with neutral beam injection (NBI) for core plasma fueling by energetic particles automatically leads to ‘the best possible confinement regime’, uniquely compatible with burning plasma. This paper outlines the conceptual details of the 24/7-FLiLi divertor for a JET size tokamak. The main focus is in regard to the physics of the low recycling regime as well as to the expected performance of the burning plasma. In comparison with the results of 1994 on TFTR and 1997 on JET, the projected performance is astonishing: fusion power –26 MW, fusion efficiency , tritium burn up 7.8%–8.7% with modest NBI power MW, and energy keV. This new regime could resolve the outstanding plasma physics issues related to burning plasma that are unsolvable with the currently dominant approach.

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“…Without edge cooling, the plasma is thermally decoupled from the wall, permitting the edge temperature to approach the core temperature [2]. The resulting flat temperature gradients eliminate thermal conduction, and energy losses become limited by particle diffusion [3]. This new confinement regime has the potential to dramatically simplify * Author to whom any correspondence should be addressed.…”

Section: Introductionmentioning

confidence: 99%

Toroidal plasma acceleration due to NBI fast ion losses in LTX-β

Hughes¹,

Capecchi²,

Elliott³

et al. 2021

Plasma Phys. Control. Fusion

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The recent Lithium Tokamak Experiment-Beta (LTX-β) upgrade includes the addition of neutral beam injection (NBI) in the same direction as the plasma current (co-I P ) and a new toroidal Mirnov array for MHD characterization. In initial NBI experiments, a spontaneously rotating n = 1 MHD mode is seen to accelerate during NBI in the counter-beam direction, accompanied by a rise in electron density consistent with the beam-injected inventory but without a clear increase in plasma pressure. Together with analytic and numerical modeling of beam optics and fast ion confinement, these observations indicate the prompt loss of all or nearly all beam ions. However, the same modeling also suggests that planned upgrades to the Ohmic heating system should provide the fast ion confinement necessary for beam heating and core fueling. A simple analytic model relates the momentum confinement time τ ϕ to the observed evolution of mode rotation due to the combination of NBI momentum coupling, fast ion loss ⃗ J × ⃗ B, and anomalous viscous torques, yielding τ ϕ values consistent with past measurements of electron energy confinement time τ E,e .

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LiWALL FUSION — THE NEW CONCEPT OF MAGNETIC FUSION

Cited by 6 publications

References 4 publications

Understanding disruptions in tokamaks

Understanding disruptions in tokamaks

On a burning plasma low recycling regime with P _DT = 23–26 MW, Q _DT = 5–7 in a JET-like tokamak

Toroidal plasma acceleration due to NBI fast ion losses in LTX-β

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LiWALL FUSION — THE NEW CONCEPT OF MAGNETIC FUSION

Cited by 6 publications

References 4 publications

Understanding disruptions in tokamaks

Understanding disruptions in tokamaks

On a burning plasma low recycling regime with P DT = 23–26 MW, Q DT = 5–7 in a JET-like tokamak

Toroidal plasma acceleration due to NBI fast ion losses in LTX-β

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On a burning plasma low recycling regime with P _DT = 23–26 MW, Q _DT = 5–7 in a JET-like tokamak