4.7 Article

Development and characterization of advanced neutron multiplier materials

期刊

JOURNAL OF NUCLEAR MATERIALS
卷 543, 期 -, 页码 -

出版社

ELSEVIER
DOI: 10.1016/j.jnucmat.2020.152593

关键词

beryllium; titanium beryllides; neutron irradiation

资金

  1. Euratom research and training programme [633053]

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Neutron multiplier materials are crucial for tritium production and fuel cycle closure in fusion reactors. The traditional pebble bed concept faces challenges such as tritium accumulation and safety issues, leading to the exploration of advanced materials like beryllides. The transition to beryllides allows for a shift from the pebble bed concept to a solid hexagonal block-based one, addressing issues of tritium retention and safety concerns.
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 degrees 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. (C) 2020 Karlsruhe Institute of Technology. Published by Elsevier B.V.

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