Investigation of hydrogen isotopes interaction with ITER and DEMO reactors structural materials in the Republic of Kazakhstan

Study of retention and permeability of hydrogen isotopes in structural materials is one of the key problems for design and operation of thermonuclear reactors. Given article is denoted to investigations conducted within the framework of the ITER Project in Kazakhstan and to support of studies of characteristics of structural materials of DEMO reactor. The basic direction of the work is a verification of fusion reactor safety. The basic investigated materials are stainless steel, vanadium alloys (V4Cr4Ti, V6Cr5Ti), low-activated steels such as MANET or F82H, beryllium, Li17Pb83 eutectics and ceramics Li2TiO3 which are considered to be structural materials of thermonuclear reactors. The basic parameters of hydrogen isotope interaction with the specified structural materials have been determined by permeation and thermo-stimulated gas release techniques in the process of reactor irradiation. As a irradiation source the reactor IVG.1M of National Nuclear Center of the Republic of Kazakhstan is used. For carrying out of research work in the support of ITER Project and for personal training in Republic Kazakhstan the creation of Kazakhstan tokamak (KTM) for material studies is undergoing. At present time are elaborated the detailed design of installation, the program of research studies. (author)