Boronization in Tore Supra

Gauthier, E.; Grisolia, Christian; Grosman, A.; Hess, W.; Hutter, T.; Michelis, C. De; Monier‐Garbet, P.; Poutchy, L.; Roth, J.

doi:10.1016/s0022-3115(06)80114-5

Cited by 30 publications

(12 citation statements)

References 3 publications

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“…Even when the plasma confinement does not improve, the use of wall conditioning permits density and recycling control, greatly widening the operational space in JET [56], ASDEXUpgrade [57], and during long-duration (> 1 minute) plasma discharges on Tore Supra [58].…”

Section: 31)mentioning

confidence: 99%

“…Liquid lithium is being explored as a potential plasma facing material in fusion reactors [55], and its use may open very attractive, stable, high beta 'zero recycling' regimes [56]. Even when the plasma confinement does not improve, the use of wall conditioning permits density and recycling control, greatly widening the operational space in JET [57], ASDEX-Upgrade [58], and during long duration (>1 min) plasma discharges on Tore Supra [59]. Although a predictive theory of the relation between wall composition and plasma performance is lacking, some correlations of 'cause' and 'effect' are emerging.…”

Section: Plasma Interaction With the Main Chamber Wallmentioning

confidence: 99%

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Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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The major increase in discharge duration and plasma energy in a next step DT fusion reactor will give rise to important plasma-material effects that will critically influence its operation, safety and performance. Erosion will increase to a scale of several centimetres from being barely measurable at a micron scale in today's tokamaks. Tritium co-deposited with carbon will strongly affect the operation of machines with carbon plasma facing components. Controlling plasma-wall interactions is critical to achieving high performance in present day tokamaks, and this is likely to continue to be the case in the approach to practical fusion reactors. Recognition of the important consequences of these phenomena stimulated an internationally co-ordinated effort in the field of plasma-surface interactions supporting the Engineering Design Activities of the International Thermonuclear Experimental Reactor project (ITER), and significant progress has been made in better understanding these issues. The paper reviews the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next step fusion reactors. Two main topical groups of interaction are considered: (i) erosion/redeposition from plasma sputtering and disruptions, including dust and flake generation and (ii) tritium retention and removal. The use of modelling tools to interpret the experimental results and make projections for conditions expected in future devices is explained. Outstanding technical issues and specific recommendations on potential R&D avenues for their resolution are presented.

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Section: 31)mentioning

confidence: 99%

Section: Plasma Interaction With the Main Chamber Wallmentioning

confidence: 99%

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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“…Liquid lithium is being explored as a potential plasma facing material in fusion reactors [36], and its use may open very attractive, stable, high beta "zero recycling" regimes [37]. Even when the plasma confinement does not improve, the use of wall conditioning permits for density and recycling control, greatly widening the operational space in JET [38], ASDEX-Upgrade 24 [39], and during long duration (>1 min) plasma discharges on Tore Supra 25 [40][41][42].…”

Section: Introductionmentioning

confidence: 99%

Safety Analysis in Large Volume Vacuum Systems Like Tokamak: Experiments and Numerical Simulation to Analyze Vacuum Ruptures Consequences

Malizia

Lupelli

Richetta

et al. 2014

Advances in Materials Science and Engineering

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The large volume vacuum systems are used in many industrial operations and research laboratories. Accidents in these systems should have a relevant economical and safety impact. A loss of vacuum accident (LOVA) due to a failure of the main vacuum vessel can result in a fast pressurization of the vessel and consequent mobilization dispersion of hazardous internal material through the braches. It is clear that the influence of flow fields, consequence of accidents like LOVA, on dust resuspension is a key safety issue. In order to develop this analysis an experimental facility is been developed: STARDUST. This last facility has been used to improve the knowledge about LOVA to replicate a condition more similar to appropriate operative condition like to kamaks. By the experimental data the boundary conditions have been extrapolated to give the proper input for the 2D thermofluid-dynamics numerical simulations, developed by the commercial CFD numerical code. The benchmark of numerical simulation results with the experimental ones has been used to validate and tune the 2D thermofluid-dynamics numerical model that has been developed by the authors to replicate the LOVA conditions inside STARDUST. In present work, the facility, materials, numerical model, and relevant results will be presented.

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“…However, the control of oxygen inventory and its release in the plasma as H 2 O, CO and CO 2 molecules has been a big problem for these machines. To reduce plasma contamination, a large effort has been made to optimize cleaning and conditioning procedures, which have led, as a final step, to cover in situ the vacuum chamber with boron [1][2][3][4][5] and silicon coatings [2,6]. These materials are, in fact, very suitable as their properties form tight bonds with oxygen and carbon.…”

Section: Introductionmentioning

confidence: 99%

Effects of wall boron coating on FTU, an all metallic and carbon free medium size tokamak

Apicella¹,

Mazzitelli²,

Esposito³

et al. 2005

Nucl. Fusion

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Boronization of FTU tokamak strongly affects its gas recycling, impurity concentration and its temporal evolution. Two main phases are distinguished. In the first one, lasting about 60 discharges, with the machine fully boronized, the radiation losses decrease from 80% to 40% and the impurity content drops from Z eff = 6 to Z eff ≈ 1.5 at n e ≈ 0.35×10 20 m −3 in ohmic conditions. In the second phase, lasting >500 discharges, with the B film eroded from the TZM toroidal limiter surface but not from the SS walls, the reduction of radiated power (≈60%) and impurities (Z eff ≈ 2.0) though smaller, is still important with respect to pre-boronization, allowing for optimization of plasma characteristics up to the maximum RF power so far injected (2.6 MW ≈ 1.6 MW m −3). The recycling properties of the B film are fully stabilized, making the plasma operations much more reliable, while the gettering properties are preserved and they maintain the oxygen below n O 0.5%.

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Boronization in Tore Supra

Cited by 30 publications

References 3 publications

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

Safety Analysis in Large Volume Vacuum Systems Like Tokamak: Experiments and Numerical Simulation to Analyze Vacuum Ruptures Consequences

Effects of wall boron coating on FTU, an all metallic and carbon free medium size tokamak

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