Experimental facilities for investigation of structural material properties for fusion reactor under irradiation

• Published in: Journal of nuclear materials 1992-09, Vol.191, p.1363-1366
• Main Authors: Kalinin, G.M., Strebkov, Yu.S., Sidorenkov, A.V., Zyryanov, A.P., Barsanov, V.I., Shushlebin, V.V., Rybin, V.V., Vinokurov, V.F., Odintsov, N.B., Zykanov, V.A., Shamardin, V.K., Kazakov, V.A.
• Format: Article
• Language: English
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/0022-3115(92)90697-J

The study of structural and breeding materials for fusion reactors covers a wide range of investigations including the effect of different operating factors; irradiation is the main factor. This paper presents basic reactor characteristics, the types of investigations on structural and breeding materials carried out at these reactors, and the reactor irradiation conditions. The design of equipment used for parameter control during the irradiation is also discussed. CM-2 and BOR-60 reactors are primarily used to irradiate structural materials for the blanket, first wall and divertor at temperatures of 80 and 350°C and fluences up to 5 × 10 22 n/cm 2. The IVV-2 reactor is used to investigate breeding blanket materials and to study the problems of hydrogen/tritium permeability and recovery from Li-Pb eutectic and through 0.4C-16Cr-11Ni-3Mo-Ti steel. In addition, there are facilities for carrying out irradiation experiments at cryogenic temperatures as well as in different media.