July 2026

Journal

Comparative neutron-irradiation effects on thermal conductivity degradation and dimensional stability of TiC, TiB2, and ZrB2 at 200–1000 °C

By:
Lin, Yan-Ru ; Koyanagi, Takaaki ; Zinkle, Steven J; Haque, Mobashera Saima; Ouyang, Mingxi; Sprouster, David; Kato, Yutai
Journal Name:
Journal of Nuclear Materials
Page Number:
156897
Volume:
632
Publication Date:
July 22, 2026
View DOI Listing:
https://doi.org/10.1016/j.jnucmat.2026.156897

Abstract

Ultra-high-temperature ceramics (UHTCs), including TiC, Ti11B₂, and Zr11B₂, show great potential for plasma-facing components due to their excellent high-temperature properties prior to irradiation. However, their response to neutron irradiation remains insufficiently understood, limiting robust assessment of their viability for fusion energy applications. This study examines the thermal conductivity, dimensional stability and microstructure of TiC, TiB₂, and ZrB₂ following neutron irradiation at temperatures of 200–1000 °C and fast neutron fluences of 2.0 × 1025 to 1.1 × 1026 n/m2 (E > 0.1 MeV). Lattice swelling measured by synchrotron X-ray diffraction in all three UHTCs was maximized at 200 °C and decreased with increasing irradiation temperature, with no evidence of amorphization observed at 200 °C. Above 600 °C, significant macroscopic volume swelling was observed in irradiated Ti11B₂ and Zr11B₂, but not in TiC, likely due to cavity formation in the diborides. The post-irradiation thermal conductivity, measured at the irradiation temperature, ranged from 28 to 45 W/m·K, representing a 34–45% reduction relative to the unirradiated material. Notably, neutron-irradiated UHTCs exhibit recoverable thermal conductivity at elevated temperatures, comparable to ferritic–martensitic steels and potentially superior to W when transmutation effects are considered, highlighting promise for shielding or armor plasma-facing components. At 600 °C, both thermal conductivity degradation and lattice swelling saturated at doses exceeding 2–4 dpa.