Published December 1992 | Version v1
Journal article

ITER edge-plasma conditions versus pump configuration

Creators

  • 1. Los Alamos National Lab., NM (United States)

Description

Two-dimensional fluid simulations of ITER double-null divertor scrape-off layer plasma conditions have been limited to considerations of a single outboard divertor plate with up/down symmetry assumed. The present work evaluates the effect of pumping at only one plate on particle flow patterns and divertor power loads. Pumping only at one plate reduces sheath temperatures at both plates, but increases the heat flux at the pumped plate. The physics assumptions for separatrix density (nSEP=/3.5) and for radial particle diffusivity (D=0.66 m2/s) used in the simulation of ITER edge plasma result in particle throughputs two orders of magnitude greater than that required for acceptable fusion-product ash removal rates. The main-plasma particle confinement time, however, is an order of magnitude shorter than the transport energy confinement time, τE. Plasmas (D=0.04 m2/s) which would have τp∝τE are evaluated and are found to have unacceptably high plasma temperatures and heat flux at the plate. Ash removal rates are still acceptable. A plasma recylce coefficient (at the divertor plate) of R=0.965 reduces the particle throughput by a factor of 2.8 below the case without recycle. (orig.)

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
196-198
Journal Page Range
p. 765-769.
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
10. biennial international conference on plasma surface interactions (PSI-10) in controlled fusion devices.
Dates
30 Mar - 3 Apr 1992.
Place
Monterey, CA (United States).

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
24034786
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
COMPUTERIZED SIMULATION; CONFINEMENT TIME; DIVERTORS; ELECTRON TEMPERATURE; HEAT FLUX; ITER TOKAMAK; PLASMA SCRAPE-OFF LAYER; RECYCLING; THEORETICAL DATA; TWO-DIMENSIONAL CALCULATIONS
Descriptors DEC
BOUNDARY LAYERS; CLOSED PLASMA DEVICES; DATA; INFORMATION; LAYERS; NUMERICAL DATA; SIMULATION; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information

Contract/Grant/Project number
Contract DE-AC02-76CH03073