Divertor heat flux reduction by D sub 2 injection in DIII-D

Conference · Fri May 01 00:00:00 EDT 1992

OSTI ID:5222469

Petrie, T W; Groebner, R J; Leonard, A W; Lippmann, S I; Mahdavi, A M; West, W P ^[1]; Buchenauer, D; Campbell, R B ^[2]; Hill, D N; Allen, S L; Futch, A H; Resink, M E ^[3]; Klepper, C C ^[4]

---

1. General Atomics, San Diego, CA (United States)
2. Sandia National Labs., Livermore, CA (United States)
3. Lawrence Livermore National Lab., CA (United States)
4. Oak Ridge National Lab., TN (United States)

D{sub 2} gas injected into ELMing H-mode discharges in DIII-D reduced total integrated heat flux to the divertor by {approximately}2{times} and peak heat flux by {approximately}5{times}, with only modest degradation to plasma stored energy. Steady gas injection without particle pumping results in eventual degradation in stored energy. The initial reduction in peak heat flux at the divertor tiles may be primarily due to the increase in radiated power from the X-point/divertor region. The eventual formation of a high density region near the X-point appears to play a role in momentum (and energy) transfer from the flux surfaces near the outboard strike point to flux surfaces farther out into the scrapeoff. This may also contribute to further reduction in peak heat flux.

• Research Organization: General Atomics, San Diego, CA (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC03-89ER51114
• OSTI ID: 5222469
• Report Number(s): GA-A-20899; CONF-920311-12; ON: DE92014232
• Resource Relation: Conference: 10. international conference on plasma-surface interactions in controlled fusion devices, Monterey, CA (United States), 30 Mar - 3 Apr 1992
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Fu
DEUTERIUM
BEAM INJECTION
DIVERTORS
HEAT FLUX
DOUBLET-3 DEVICE
EDGE LOCALIZED MODES
ELECTRON DENSITY
ELECTRON TEMPERATURE
H-MODE PLASMA CONFINEMENT
MOMENTUM TRANSFER
PLASMA PRESSURE
PLASMA SCRAPE-OFF LAYER
BOUNDARY LAYERS
CLOSED PLASMA DEVICES
CONFINEMENT
HYDROGEN ISOTOPES
INSTABILITY
ISOTOPES
LAYERS
LIGHT NUCLEI
NUCLEI
ODD-ODD NUCLEI
PLASMA CONFINEMENT
PLASMA INSTABILITY
PLASMA MACROINSTABILITIES
STABLE ISOTOPES
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
700420* - Fusion Technology- Plasma-Facing Components- (1992-)
700460 - Fusion Technology- Heating & Fueling Systems
Fuels- (1992)