Physical and Engineering Constraints for Tokamak Reactors with Helical Coils
- 1 September 1983
- journal article
- research article
- Published by Taylor & Francis in Nuclear Technology - Fusion
- Vol. 4 (2P3) , 1314-1319
- https://doi.org/10.13182/fst83-a23038
Abstract
We present an analytical and numerical analysis of a tokamak reactor with a set of helical coils added in order to eliminate plasma disruptions. The optimal helical configuration was found to be a set of continuous, ℓ = 2 stellarator coils which are made of copper and are internal to the toroidal field coils, ℓ being the number of poloidal field periods. (The optimization process did not include evaluation of the viability of a modular stellarator reactor). Scaling laws were developed for this optimal configuration, and a series of parametric scans are performed with varying assumptions for the forces on the helical coils and the ratio of helical coil transform to plasma transform (M*). The option space available for attractive reactor designs is strongly constrained and involves large forces on the helical coils, low q plasma operation (q being the plasma safety factor), and moderately low M* (3 to 5). Numerical calculations showed that M* must be > 3 in order to obtain well defined flux surfaces...Keywords
This publication has 2 references indexed in Scilit:
- Numerical determination of axisymmetric toroidal magnetohydrodynamic equilibriaJournal of Computational Physics, 1979
- Characteristics of high-density tokamak ignition reactorsNuclear Fusion, 1976