Abstract
The objective of this work is to carry out the tests of the KTM tokamak lithium divertor model as well as develop recommendations on the use of lithium technologies in tokamak-reactors. Li-technology will be developed and a Na-K cooled KTM tokamak lithium divertor module will be designed and tested as a result of the project completion. It will be possible to operate the renewed lithium surface module under specific heat loads from 2 to 10 MW/m2 while in a quasi-stationary mode, discharge duration of up to ~5 s. The technical project proposal; design scheme and sketches; and procedure development for preparation, protection, cleaning and rehabilitation of lithium CPS (capillary-porous system) surfaces in tokamak conditions have been completed. The design substantiation calculations; technique development for lithium handling in tokamak conditions; and confirming experiments on T-11M tokamak to prove the procedures developed are still in a progress. The study of both the lithium influence on the KTM plasma discharge parameters and specific power load on the plasma facing components as well as the selection of optimum operational modes of the lithium divertor will be accomplished after completion of the start-up and adjustment tests of the KTM tokamak divertor demonstration models.