A new helical-axis heliotron device, Heliotron J, is now being constructed
at the institute of Advanced Energy of Kyoto University with the goal of de
monstrating its improved helical confinement property in the helical-axis h
eliotron line. The design feature of Heliotron J is, as compared with that
of Heliotron E, the reduced neoclassical transport (near the tokamak level
according to the DKES code) and the enhanced average beta limit (4% for the
Mercier criterion) with small bootstrap current, which carries the potenti
al for developing the currentless 'quasi-isodynamic' optimization. The devi
ce parameters are as follows: the major plasma radius of 1.2 m, the average
plasma minor radius of 0.1-0.2 m, the magnetic field strength on the magne
tic axis of 1.5 T, the vacuum rotational transform of 0.2-0.8 with a low ma
gnetic shear, and the magnetic well depth of 1.5% at the plasma edge, with
heating systems such as ECH(0.5 MW), NBI(1.5 MW), and ICRF(2.5 MW). The fea
sibility of the helical-axis heliotron concept and its ability to explore h
igh-quality confinement surfaces with a divertor will be fully tested in He
liotron J. The first plasma was planned to be produced in the autumn of 199
9.