Speaker
Description
A.Shaimerdenov, T.Kulsartov, I.Kenzhina, Zh.Zaurbekova, Sh.Gizatulin, S.Askerbekov
The Institute of Nuclear Physics, 1 Ibragimov st., Almaty, Kazakhstan
This article provides an overview of irradiation activities on the WWR-K reactor to test ceramic blanket materials for a fusion reactor. It describes the experimental capabilities of the WWR-K reactor, the tested materials, the conditions of the irradiation test, and the results of an in-reactor study of ceramic materials.
The irradiation tests demonstrated the processes and features of tritium generation and release from ceramic materials under different conditions (temperature, neutron fluence, environment). The experimental data obtained have a practical contribution to ceramic breeder material development for ITER and DEMO.
