Accident-tolerant hybrid ceramics for fusion breeding blanket
• Li–Be–X–O is synthesized based on the prediction by the machine learning model. • Steam exposure tests at 1200 °C verified the accident tolerance of hybrid ceramics. • Two-phase hybrid ceramics can breed sufficient fuel tritium without metallic Be. • Hybrid ceramics allows a novel blanket design with enhanced safety margins. In a water-cooled ceramic breeding blanket for fusion reactors, hydrogen gas generation by steam oxidation of metallic Be compounds (i.e. neutron multiplier) in a loss-of-coolant accident (LOCA) raises major safety concerns. Li–Be hybrid ceramics has a potential to reduce hydrogen generation significantly, however, the stable compositions and structures for quaternary compositions have not been comprehensively understood. Herein, we report machine-learning based prediction, synthesis, structure, and properties of chemically stabile two-phase Li–Be–X–O hybrid ceramics. The steam exposure tests demonstrated a negligibly small H 2 generation from the two-phase powder of Li 2 BeSiO 4 and 5 at.% BeO below 1200 °C. The stability is explained by the intrinsic ionic/covalent bonding characters and little capacity for further oxidation by steam. Neutronic calculations with simplified one-dimensional model show that the two-phase hybrid cermaics has a sufficient tritium breeding capability without having metallic Be-based multiplier in the blanket. The hybrid ceramics is the first example of multi-functional oxide to breed sufficient fuel tritium with no metallic neutron multiplier, which allows a novel design of ceramic breeding blanket with enhanced safety margins during in-box LOCA.
Authors
- Taehyun Hwang (ORCID: https://orcid.org/0000-0001-8005-5279)
- Keisuke Mukai (ORCID: https://orcid.org/0000-0001-8067-8732)
- Jae-Hwan Kim (ORCID: https://orcid.org/0000-0002-2095-3031)
- Minoru Kusaba
Institutions
- The Graduate University for Advanced Studies, SOKENDAI (JP)
- National Institute for Fusion Science (JP)
- National Institutes for Quantum Science and Technology (JP)
- The Institute of Statistical Mathematics (JP)
- Research Organization of Information and Systems (JP)
Publication Details
- Journal
- Materials & Design
- Published
- 2025-04-19
- DOI
- https://doi.org/10.1016/j.matdes.2025.113964
- Primary Topic
- Nuclear Materials and Properties
- Type
- article
- Field-Weighted Citation Impact
- 0.00
Funders
- Japan Society for the Promotion of Science