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Helium transport and exhaust studies in DIII-D

Journal Article · · Fusion Technology
OSTI ID:41462
; ; ;  [1]; ; ; ;  [2];  [3];
  1. Oak Ridge National Lab., TN (United States)
  2. General Atomics, San Diego, CA (United States)
  3. Univ. of California, Berkeley, CA (United States)
+ Show Author Affiliations
A better understanding of helium transport in the plasma core and edge in enhanced confinement regimes is now emerging from recent experimental studies on DIII-D. Overall, the results are encouraging with significant helium exhaust obtained in a diverted, ELMing H-mode plasma, with {tau}*{sub He}/{tau}{sub E} {approximately} 10 and transport studies indicating that D{sub He}/{Chi}{sub eff} {approximately} 1 in all plasma conditions studied to date. However, measurements in the core and pumping plenum show a significant dilution of helium as it flows from the plasma core to the pumping plenum. Such dilution could be the limiting factor in the overall removal rate of helium in a reactor system.
DOE Contract Number:
AC05-84OR21400; AC03-89ER51114
OSTI ID:
41462
Report Number(s):
CONF-940630--
Journal Information:
Fusion Technology, Journal Name: Fusion Technology Journal Issue: 3 Vol. 26; ISSN 0748-1896; ISSN FUSTE8
Country of Publication:
United States
Language:
English

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Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ALPHA PARTICLES
CHARGED-PARTICLE TRANSPORT
DIVERTORS
DOUBLET-3 DEVICE
H-MODE PLASMA CONFINEMENT
PUMPING