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.

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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

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article

Accident-tolerant hybrid ceramics for fusion breeding blanket

Taehyun Hwang, Keisuke Mukai, Jae-Hwan Kim, Minoru Kusaba
Materials & Design
Nuclear Materials and Properties
article

Accident-tolerant hybrid ceramics for fusion breeding blanket

Taehyun Hwang, Keisuke Mukai, Jae-Hwan Kim, Minoru Kusaba
article en

Abstract

• 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.

Materials & DesignVol. 253
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)
Japan Society for the Promotion of Science
Zero hunger
Openalex Percentile: Top 94%
Nuclear Materials and Properties
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