Аннотация
Metallic beryllium has long been considered as a candidate neutron multiplier material in the solid-state breeder blanket of a fusion reactor. However, beryllium intermetallic compounds (beryllides) are currently preferred due to lower swelling and higher stability at high temperatures. One of the promising and less-studied beryllium compounds is chromium beryllide (CrBe 12 ), which is considered a candidate material for the neutron multiplier in the modular blanket of the future DEMO fusion reactor. Experimental data on the behavior of CrBe 12 in a neutron field are insufficient to conclude that it is suitable for a fusion reactor. In this regard, work was started at the WWR-K reactor to study the corrosion stability of CrBe 12 , manufactured at the Ulba Metallurgical Plant, under reactor irradiation conditions. This paper presents the developed design of an irradiation capsule that forms conditions close to operational conditions in fusion reactors. The results of comprehensive neutron and thermophysical calculations are presented, justifying the irradiation conditions and their predicted values in the WWR-K reactor. The reactor irradiation plan and methodology for the corrosion resistance study of CrBe 12 samples are described.