About this Abstract |
Meeting |
2022 TMS Annual Meeting & Exhibition
|
Symposium
|
Materials Systems for the Future of Fusion Energy
|
Presentation Title |
Development, Production, and Qualification of Berrylide Neutron Multiplier Parts for the He Cooled Breeding Blanket |
Author(s) |
Ramil Gaisin, Michael Duerrschnabel, Michael Klimenkov, Pavel Vladimirov, Sergey Udartsev |
On-Site Speaker (Planned) |
Ramil Gaisin |
Abstract Scope |
In the helium-cooled blanket concept for the DEMO fusion reactor, solid blocks of titanium beryllide TiBe12 will multiply and moderate neutrons to produce tritium in lithium ceramics. However, the production of large blocks faced many issues due to the extreme hardness and fragility of beryllides. Various casting and powder metallurgy methods were tested before a series of massive titanium beryllide blocks with dimensions up to Ø150mm×200mm was obtained. The resulting blocks have a homogeneous microstructure consisting of single-phase TiBe12 grains with traces of residual beryllium and beryllium oxide. In terms of specific compressive strength, the obtained TiBe12 surpasses all materials, except diamond, in the 700–1000°C temperature range. Long-term thermal cycling tests with rapid heating and cooling, simulating operation in a fusion reactor, showed high resistance of beryllides to thermal shocks. The results obtained are supported by extensive microstructural investigations. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Powder Materials, High-Temperature Materials |