Tokamak Physics Experiment poloidal field design
The Tokamak Physics Experiment (TPX) will have a poloidal field system capable of full inductive operation poloidal for approximately a 20-s flattop and, with superconducting toroidal and poloidal field coils and non-inductive current drive, it will be capable of true steady-state operation. The poloidal field design is based on the ideal MHD equilibrium model as implemented in the TEQ code developed at LLNL. The PF coils are arranged in an up-down symmetric configuration, external to the TF coils. The TPX diverted plasma will have an aspect ratio of 4.5 and is highly shaped with a nominal elongation of 2 and triangularity of approximately 0.8 as measured at the separatrix. The tokamak design is based on a high-current (q{sub {psi}}=3) plasma scenario and a low current scenario. Each scenario has an operational flexibility requirement which is defined as a region of plasma pressure and inductivity ({beta}{sub N} {minus} l{sub i}) space, where the plasma shape is constrained to keep the divertor configuration operational. Single-null plasma configurations are feasible, even with the same divertor hardware, by operating the PF coils asymmetrically. Recently applied optimization techniques have improved the capability of the PF system without additional cost.
- Research Organization:
- Lawrence Livermore National Lab., CA (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 10189192
- Report Number(s):
- UCRL-JC-114268; CONF-931018-16; ON: DE94001542
- Resource Relation:
- Conference: Symposium on fusion engineering,Hyannis, MA (United States),11-15 Oct 1993; Other Information: PBD: 6 Oct 1993
- Country of Publication:
- United States
- Language:
- English
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