In-situ tritium recovery experiment from lithium oxide under high neutron fluence
1984; Elsevier BV; Volume: 123; Issue: 1-3 Linguagem: Inglês
10.1016/0022-3115(84)90191-0
ISSN1873-4820
AutoresT. Kurasawa, H. Takeshita, Hiroyuki Watanabe, Hiroshi Yoshida, Yuji Naruse, Takejiro Miyauchi, K. Mimura, H. Umei,
Tópico(s)Nuclear materials and radiation effects
ResumoThe breeding blanket is a key component of the fusion reactor because it directly involves tritium breeding and energy extraction, both of which are critical to development of fusion power. The lithium ceramics continue to show promise as candidate breeder materials. This promise was also recognized by the International Thermonuclear Experimental Reactor (ITER) design team in its selection of ceramics as the first option breeder material. Blanket design studies have indicated areas in the properties data base that need further investigation. Current studies are focusing on issues such as tritium release behavior at high burnup, changes in thermophysical properties with burnup, compatibility between ceramic breeder and beryllium multiplier, and phase changes with burnup. Laboratory and in-reactor tests are underway, some as part of an international collaboration for development of ceramic breeder materials.
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