All-remote configuration for the ETR-INTOR tokamak design

The objective of this study is to develop a comparison of the costs and engineering implications of improving tritium containment and shielding as required for personnel access (FED-INTOR) versus adopting a totally remotely operated and maintained design (ETR-INTOR). The work presently underway has focused on developing a device configuration which is amenable to all-remote operations, reducing the biological shielding on the plasma chamber, assessing tritium containment requirements for both designs, and developing facility layouts for both designs