The ITER poloidal field configuration and operation scenario
- and others
The ITER Poloidal Field (PF) system must satisfy the following requirements. (1) ITER must have a well-controlled, single null divertor magnetic configuration with nominal plasma current 21MA and moderate plasma elongation k95 < 1.65. (2) For a variety of plasma scenarios the ITER PF system must provide: inductive breakdown and start-up in an expanding-aperture limiter configuration near the outboard first wall; an inductive current ramp-up to the nominal plasma current with a reasonable assumption of resistive loss during current ramp-up; a pulse length of 1,000s for ignition and inductively-sustained burn at nominal plasma current; plasma shutdown (following fusion power termination) in a similar contracting-aperture limiter configuration. The present design of the PF system can satisfy the ITER requirements within specified limitations.
- OSTI ID:
- 465047
- Report Number(s):
- CONF-950905--; ISBN 0-7803-2969-4
- Country of Publication:
- United States
- Language:
- English
Similar Records
Design of the outer poloidal field coil system for ITER
Impact of a poloidal divertor in ignition tokamak design