Boundary plasma modelling for ITER
Computer programs were developed to model the effect of nonaxisymmetric magnetic perturbations upon divertor heat load, and have explored what kind of externally applied perturbations are the most effective for heat load reduction without destroying core plasma confinement. We find that a carefully tuned set of coils located about 0.3 m outside the separatrix can be used to spread the heat load over about 0.1 m perpendicular to flux surfaces at the ITER divertor plate, even at a very low level of anomalous cross-field heat transport. As such a spreading would significantly extend the permissible regime of operation for ITER, we recommend that this study be pursued at the level of detail required for engineering design. In other work under this grant we are in the process of modifying the B2 code to handle correctly a non-orthogonal geometry.
- Research Organization:
- New York Univ., NY (United States). Courant Inst. of Mathematical Sciences
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- FG02-92ER54165
- OSTI ID:
- 7009859
- Report Number(s):
- DOE/ER/54165-1; ON: DE93007963
- Country of Publication:
- United States
- Language:
- English
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Boundary plasma modeling for ITER. Final report, July 1, 1992--December 31, 1994
The three-dimensional modeling of plasma edge transport and divertor fluxes during application of resonant magnetic perturbations on ITER
Related Subjects
DIVERTORS
HEATING
ITER TOKAMAK
MAGNETIC FIELD CONFIGURATIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
PROGRESS REPORT
CLOSED PLASMA DEVICES
DOCUMENT TYPES
SIMULATION
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
700430* - Fusion Technology- Magnet Coils & Fields- (1992-)