Divertor studies in high-power beam heated discharges in Doublet-III

Shimada, M.; Washizu, Masao; Sengoku, S.; Suzuki, Norio; Nagami, M.; Konoshima, S.; Matoba, T.; Miya, N.; Kobayashi, Takanori; Kasai, Masao; Kameari, A.; Abe, Mitsushi; Hirayama, Toshio; Kodama, K.; Yamamoto, T.; Kitsunezaki, A.; Kahn, C.; Hsieh, C. L.; Snider, R. T.; Groebner, R. J.; Brooks, N.H.; Burrell, K.H.

doi:10.1016/0022-3115(84)90376-3

Cited by 24 publications

(16 citation statements)

References 10 publications

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“…e is compared with this experimental result in Ref. [4]. This result indicates that X n is an increasing function of heating power.…”

Section: Fig 7 Carbon Influx Radiation Loss Edge Density and Averaged...supporting

confidence: 51%

“…However, the present observations indicate what may happen in next-generation devices with higher heating power. Furthermore, impurity accumulation has been observed in ELM-free H-mode discharges in JET [2], ASDEX [3], JFT-2M and Dili [4]. In PBX, impurities tend to accumulate at the hot core when Z eff is high, independent of L-and H-modes [5].…”

Section: Impurity Controlmentioning

confidence: 99%

See 1 more Smart Citation

Impurity control Report on the IAEA Technical Committee Meeting held at Naka, Japan, 13-15 February 1989

Itoh

Shimada

1989

Nucl. Fusion

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“…e is compared with this experimental result in Ref. [4]. This result indicates that X n is an increasing function of heating power.…”

Section: Fig 7 Carbon Influx Radiation Loss Edge Density and Averaged...supporting

confidence: 51%

Section: Impurity Controlmentioning

confidence: 99%

Impurity control Report on the IAEA Technical Committee Meeting held at Naka, Japan, 13-15 February 1989

Itoh

Shimada

1989

Nucl. Fusion

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“…Successful divertor action for impurity control was demonstrated first in the small tokamak DIVA [1]. Subsequently, extensive studies of Ohmic and neutral beam (NB) heated discharges were performed in medium size tokamaks such as ASDEX [2,3], Dili [4] and PDX [5]. The three large tokamaks are JET, TFTR and JT-60 [6]; the latter is unique because it has a closed divertor chamber.…”

Section: Introductionmentioning

confidence: 99%

Radiation losses and global power balance of JT-60 plasmas

et al. 1990

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The radiation losses and the global power balance for Ohmic and neutral beam heated plasmas have been investigated in different JT-60 configurations. Discharges with a TiC coated molybdenum wall and with a graphite wall, with limiter, outer and lower X-point configurations have been studied by bolometric measurements, thermocouples and an infrared TV camera. In neutral beam heated outer X-point discharges with a TiC coated molybdenum first wall, the radiation loss of the main plasma was very low (10% of the absorbed power). The radiation loss due to oxygen was dominant in this case. On the contrary, in discharges with TiC coated molybdenum limiters the radiation loss was very high (>60% of the absorbed power). In the discharges with a graphite wall the radiated power from the main plasma was 20-25% for both limiter and lower X-point configurations. In lower X-point discharges the main contributor to the radiation loss was oxygen, whereas in limiter discharges the loss due to carbon was equal to the loss due to oxygen. The radiation loss from the lower X-point divertor increased with increasing electron density of the main plasma.

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“…Stable divertor discharges with plasma currents up to 1.6 MA have been achieved and the divertor function as established in smaller-size tokamaks [2,3] has been confirmed in JT-60 with a compact poloidal divertor having an outer divertor separatrix.…”

Section: Some Initial Experimental Resultsmentioning

confidence: 98%