Operating conditions of the BPX divertor [electronic resource].
- Published
- Washington, D.C. : United States. Dept. of Energy, 1991.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: (5 pages) : digital, PDF file
- Additional Creators
- Lawrence Livermore National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- In this paper we discuss the expected operating conditions at the divertor of the BPX tokamak (Burning Plasma Experiment), the next- step US tokamak proposed for the study of self-heated plasmas at Q {approx equal} 5 to ignition. In this double-null device (κ {approx equal} 2), the predicted first-wall loading is high because of is compact size (R = 2.6m, α = 0.8m, I{sup p} = 10.6 MA, and B{sub T}) and its high projected fusion power output (100--500 MW with up to 20 MW of ICRH). Present designs call for inertially cooled carbon-based target plate material and X-point sweeping to handle the divertor heat flux during the 3--5 s flat-top at full power. The X-point is maintained about 15--20 cm off the target plates (a distance of ∼5m along field lines), which represents a reasonable compromise between lowering the divertor electron temperature (T{sub e,d}) by increasing the connection length, and lowering the peak divertor heat flux ({cflx q}{sub d}) by increasing the magnetic flux expansion (which is about 15--20 in this case). It is planned for the BPX device to operate with H-mode confinement; ELMs are expected because of the relatively high power flow through the edge plasma (P{sub sep} {approx equal} 0.6 MW/m² for P{sub fus} = 500 MW). The ELMs will help reduce the impurity concentration in the core plasma (Z{sub eff} {approx equal} 1.7) and keep the density down, but should not add significantly to the divertor heat flux since their measured contribution to the global power balance drops with increasing input power.
- Report Numbers
- E 1.99:ucrl-jc-105946
E 1.99: conf-910609--20
conf-910609--20
ucrl-jc-105946 - Subject(s)
- Other Subject(s)
- Compact Ignition Tokamak
- Divertors
- Operation
- Plasma Scrape-Off Layer
- Plasma Simulation
- Electron Temperature
- H-Mode Plasma Confinement
- Heat Flux
- Sputtering
- Boundary Layers
- Closed Plasma Devices
- Confinement
- Layers
- Plasma Confinement
- Simulation
- Thermonuclear Devices
- Thermonuclear Reactors
- Tokamak Devices
- Tokamak Type Reactors
- Note
- Published through SciTech Connect.
01/01/1991.
"ucrl-jc-105946"
" conf-910609--20"
"DE91015675"
International conference on systems analysis in water quality management, Berlin (Germany), 3-7 Jun 1991.
Campbell, R.; Brooks, J.N.; Hill, D.N.; Haines, J.; Rognlien, T.; Milovich, J.; Prinja, A.; Ulrickson, M.; Stotler, D.P.; Braams, B.J.; Knoll, D. - Funding Information
- W-7405-ENG-48
AC02-76CH03073
View MARC record | catkey: 14748424