Development and characterization of advanced neutron multiplier materials

Development and characterization of advanced neutron multiplier materials

•Transition from pure beryllium to beryllides as neutron multiplier material enables new “fuel-breeder pin” HCPB blanket design•Solid blocks of TiBe12 are considered in the new HCPB reference design•Feasibility of industrial fabrication of solid beryllide blocks is successfully demonstrated•Titanium...

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Bibliographic Details
Published in:Journal of nuclear materials Vol. 543; p. 152593
Main Authors: Vladimirov, Pavel V., Chakin, Vladimir P., Dürrschnabel, Michael, Gaisin, Ramil, Goraieb, Aniceto, Gonzalez, Francisco Alberto Hernandez, Klimenkov, Michael, Rieth, Michael, Rolli, Rolf, Zimber, Nikolai, Udartsev, Sergey, Kolmakov, Maxim, Vechkutov, Anatoly, Frants, Evgeniy
Format: Journal Article
Language:English
Published: Amsterdam Elsevier B.V 01-01-2021
Elsevier BV
Subjects:
Beryllides
Beryllium
Breeding
Exchanging
Fabrication
Fuel cycles
Fusion reactors
Helium
Hot extrusion
Hot pressing
Irradiation
Lithium
Material properties
Melt temperature
Melting
Modules
neutron irradiation
Nuclear engineering
Nuclear fuels
Nuclear power plants
Nuclear safety
Reactors
Retention
Titanium
titanium beryllides
Tritium
titanium beryllides
neutron irradiation
beryllium
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Summary:•Transition from pure beryllium to beryllides as neutron multiplier material enables new “fuel-breeder pin” HCPB blanket design•Solid blocks of TiBe12 are considered in the new HCPB reference design•Feasibility of industrial fabrication of solid beryllide blocks is successfully demonstrated•Titanium beryllide block survives 50 heating-cooling cycles despite anticipated intrinsic brittleness of intermetallic compounds Neutron multiplier materials are essential for self-sufficient tritium production and are closing the fuel cycle of fusion reactors. Until now, a concept of pebble bed consisting of interchanging layers of beryllium and lithium ceramic pebbles was considered for the Helium-Cooled Pebble Bed (HCPB) tritium-breeding module of the first experimental fusion reactor ITER as well as for the next demonstration fusion reactor DEMO. However, this concept depends on the availability of large amounts of pure beryllium pebbles and is also limited by its material properties like for example the tritium accumulation under irradiation. The results of tritium retention and analytical microstructural studies of beryllium pebbles obtained within the framework of the HIDOBE irradiation campaign suggest that a significant fraction of generated tritium (up to 100% below 500°C) is trapped within helium bubbles. Being negligible in the ITER tritium-breeding module (TBM), the total accumulated tritium inventory imposes severe safety issues and exceeds acceptable limits for the DEMO blanket. Therefore, advanced neutron multiplier materials such as beryllides have to be well characterized for their applicability in the HCPB blanket of DEMO and beyond. The usage of an advanced material with lower volumetric swelling, lower tritium retention, increased irradiation and chemical resistance as well as with higher melting temperature allows to switch from the pebble bed concept to a solid hexagonal block-based one. For the fabrication of titanium beryllide samples both the semi-industrial fabrication route utilizing the hot extrusion of rods and the industrial approach using vacuum hot pressing of a Be-Ti powder mixture were explored. In this contribution, we discuss reasons for the transition from pure beryllium to beryllides, respective changes of the HCPB blanket design and a successful demonstration of the feasibility of a beryllide block fabrication by an industrial method.
ISSN:0022-3115
1873-4820
DOI:10.1016/j.jnucmat.2020.152593