Irradiation Damage Behavior and Mechanism of Pressureless-Sintered ZrC Ceramics

Zirconium carbide (ZrC) is a leading candidate for advanced nuclear reactor components due to its ultra-high melting point, thermomechanical stability, and low neutron absorption. However, its irradiation damage behavior and mechanism remains underexplored. In this work, dense pressureless-sintered ZrC ceramics with low-neutron-absorption MoSi2 additives were irradiated with 500 keV He2+ ions at room temperature to peak damage levels of 0.30, 1.49, and 2.97 dpa. The changes in their microstructure, bonding states, and property were analyzed via TEM, GIXRD, Raman spectroscopy, nanoindentation, and TDTR. ZrC retained crystallinity regardless of high-density black-spot defects, while MoSi2 exhibited severe amorphization and swelling. Lattice expansion and partial Zr-C bond breakage with C-C bond formation were confirmed, with maximum hardening at 1.49 dpa and significant elastic modulus reduction at 2.97 dpa. Thermal conductivity decreased modestly and showed minimal dose dependence, indicating a saturation effect. These results elucidate defect evolution in pressureless-sintered ZrC-MoSi2 ceramics and support its application in high-irradiation nuclear environments.

Authors

Institutions

Publication Details

Journal
Materials
Published
2026-05-21
DOI
https://doi.org/10.3390/ma19102158
Primary Topic
Advanced ceramic materials synthesis
Type
article
Field-Weighted Citation Impact
0.00

Funders

Controls
|||
ALL TIME
JAN
FEB
MAR
APR
MAY
JUN
JUL
AUG
SEP
OCT
article

Irradiation Damage Behavior and Mechanism of Pressureless-Sintered ZrC Ceramics

Junping Ma, H B Wu, Z Huang, Huan Liu et al.
Materials
Advanced ceramic materials synthesis
article

Irradiation Damage Behavior and Mechanism of Pressureless-Sintered ZrC Ceramics

Junping Ma, H B Wu, Z Huang, Huan Liu, Canglong Wang, Zehua Liu, Bingbing Pei, Xishi Wu, Yitian Yang, Jianshen Han
article en

Abstract

Zirconium carbide (ZrC) is a leading candidate for advanced nuclear reactor components due to its ultra-high melting point, thermomechanical stability, and low neutron absorption. However, its irradiation damage behavior and mechanism remains underexplored. In this work, dense pressureless-sintered ZrC ceramics with low-neutron-absorption MoSi2 additives were irradiated with 500 keV He2+ ions at room temperature to peak damage levels of 0.30, 1.49, and 2.97 dpa. The changes in their microstructure, bonding states, and property were analyzed via TEM, GIXRD, Raman spectroscopy, nanoindentation, and TDTR. ZrC retained crystallinity regardless of high-density black-spot defects, while MoSi2 exhibited severe amorphization and swelling. Lattice expansion and partial Zr-C bond breakage with C-C bond formation were confirmed, with maximum hardening at 1.49 dpa and significant elastic modulus reduction at 2.97 dpa. Thermal conductivity decreased modestly and showed minimal dose dependence, indicating a saturation effect. These results elucidate defect evolution in pressureless-sintered ZrC-MoSi2 ceramics and support its application in high-irradiation nuclear environments.

MaterialsVol. 19(10)
Ningbo University (CN), Chinese Academy of Sciences (CN), Institute of Modern Physics (CN), Ningbo Institute of Industrial Technology (CN)
National Natural Science Foundation of China, Chinese Academy of Sciences, Youth Innovation Promotion Association, Natural Science Foundation of Zhejiang Province
Openalex Percentile: Top 11%
Advanced ceramic materials synthesis
AI Navigator

Ask Laika to Summarize, Analyze, and Connect papers live on the map.

Summarize Papers & Methodologies

Extract key findings, datasets, and comparative methods across publications.

Benchmark Rankings & Visual Analytics

Rank top research institutions, authors, funders, topics, and journals by Field-Weighted Citation Impact (FWCI) and paper volume with instant charts.

Connect Distant Disciplines

Bridge topological clusters on the map to find hidden collaborative intersections.