Studies of global energy confinement in TFTR supershots

Strachan, J.

doi:10.1088/0029-5515/34/7/i07

Cited by 26 publications

(20 citation statements)

References 12 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Page 21 a strong adverse dependence of confinement upon the influx rates of carbon and deuterium measured spectroscopically (Strachan 1994). One consequence of an increased influx of carbon and deuterium is to broaden the density profile and reduce the depth of penetration by the neutral beam.…”

Section: Supershotmentioning

confidence: 99%

Results from deuterium-tritium tokamak confinement experiments

Hawryluk

1998

Rev. Mod. Phys.

123

View full text Add to dashboard Cite

Recent scientific and technical progress in magnetic fusion experiments has resulted in the achievement of plasma parameters (density and temperature) which enabled the production of significant bursts of fusion power from deuterium-tritium fuels and the first studies of the physics of burning plasmas. The key scientific issues in the reacting plasma core are plasma confinement, magnetohydrodynamic (MHD) stability, and the confinement and loss of energetic fusion products from the reacting fuel ions. Progress in the development of regimes of operation which have both good confinement and are MHD stable have enabled a broad study of burning plasma physics issues.

show abstract

Section: Supershotmentioning

confidence: 99%

Results from deuterium-tritium tokamak confinement experiments

Hawryluk

1998

Rev. Mod. Phys.

123

View full text Add to dashboard Cite

show abstract

“…Through intensive wall conditioning before a supershot experiment and accurate alignment of the limiter tiles, the blooIn event has been suppressed in normal TFTR operation, ttowever, a milder increase in the recycling rate (inferred from the edge Cu and H_, emissivity measurements) is often observed in TFTR NB] heated supershots, especially in larger major radius plasmas. Correlations between high maximum performance and low edge recycling rate has also been observed [34]. To describe this phenomenon, a "recycling parameter" is introduced:…”

Section: Discussion Of the Effects Of Recycling On The Per-formance Dmentioning

confidence: 95%

Transport effects of low (m,n) MHD modes on TFTR supershots

Chang¹,

Callen

Fredrickson

1993

View full text Add to dashboard Cite

Supershots in TFTR often suffer a performance deterioration characterized by a gradual decrease of the D-D fusion neutron yield and plasma stored energy after several hundred milliseconds of auxiliary heating. The correlation between this performance deterioration and the development of low m (the poloidal mode number), n (the toroidal mode number) MHD modes is studied through shot-to-shot comparisons and statistical data analyses. A good correlation is observed between performance deterioration and the appearance of strong 3/2 and 4/3 macroscopic modes (magnetic islands)in small major radius plasmas (R = 2.45 m). The magnetic island structures are observed using Mirnov and ECE diagnostics. The measured T_, Ti and n_ profiles show that development of the islands corresponds to a nearly constant decrement of these quantities over the core region r < rs, where rs is the mode rational surface, on a transport time scale (t > TE). The observed energy deterioration scaling, 5W/W ,,_ w/a, where w is the magnetic island width, agrees with both a local transport model and predictive numerical simulations. For larger major radius plasmas (R = 2.52, 2.60 m), a continuous increase of edge recycling rate during the neutral beam injection phase seems to have a larger effect on the performance deterioration than does the MHD.

show abstract

“…[2] shows that ;i peaked electron density profile shape is essential for peaked deposition of the neutral-beam at high density. This expression with the same coefficients is applicable to TFTR discharges tit different major radius discussed in this paper.…”

Section: Review O F the Scalings For Energy Confinement And Neutron Ymentioning

confidence: 93%

“…Since fusion reactivity scales approximately as Poulr2 (2) at a fixed toroidal field, relaxing the existing constraints imposed by the plasnia stability even by a modest amount can lead to a significant increase in fusion power production. In this regard, an extensive body of research has been, and continues to be conducted to better understand and characterize the stability limits of tokamak plasmas I20 1.…”

Section: Stability and Optimized Fusion Power Productionmentioning

confidence: 99%

Fusion reactivity, confinement, and stability of neutral-beam heated plasmas in TFTR and other tokamaks

Park¹,

Sabbagh²

1996

View full text Add to dashboard Cite

The hypothesis that the heating beam fueling profile shape connects the edge condition and improved core confinement and fusion reactivity is extensively studied on TFTR and applied to other tokamaks.The derived absolute scaiings [Ref.3) based on beam fueling profile shape for the stored energy and neutron yield can be applied to the deuterium discharges at different major radii in TFTR. These include Supershot, High poloidal beta, L-mode, and discharges with a reversed shear (RS) magnetic configuration. These scalings are also applied to deuterium-tritium discharges. The role of plasma parameters, such as plasma ciirren t. Isdo2(p), edge safety factor, c~.sdo5(a), and toroidal field, Bsdo2(T), in the performance and stability of the discharges is explicitly studied. Based on practical and externally controllable plasma parameters, the limitation and optimization of fusion power production of the present TFTR is investigated and a path for ii discharge condition with fusion power gain, Q > 1 is suggested based on this study. Similar physics interpretation is provided for beam heated discharges on other major tokamaks.

show abstract

Studies of global energy confinement in TFTR supershots

Cited by 26 publications

References 12 publications

Results from deuterium-tritium tokamak confinement experiments

Results from deuterium-tritium tokamak confinement experiments

Transport effects of low (m,n) MHD modes on TFTR supershots

Fusion reactivity, confinement, and stability of neutral-beam heated plasmas in TFTR and other tokamaks

Contact Info

Product

Resources

About