This paper presents a design of tokamak plasma with use of the high temperature superconducting coils as plasma stabilizer. Having regard to the current situation of the ITER project, two cases of designs were investigated: a smaller machine which has the same mission of the ITER/RCO (Q = 10), and an ignition machine which has the same major radius as ITER/RCO (R = 6.1 m). The same data base and formulas as ITER are here used and any innovative technology other than the HTSC stabilizing coils is not assumed.
ASJC Scopus subject areas
- Civil and Structural Engineering
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering