Abstract
This study investigates the microstructural evolution of pure tungsten irradiated under thermal-neutron shielded and mixed spectrum conditions in the High Flux Isotope Reactor (HFIR). Four samples were irradiated at temperatures from 570 °C to 1130 °C up to 0.73 dpa. Neutron spectrum significantly influenced the accumulation of transmutation products, with Re +Os content estimated at ∼0.3–0.6% under thermal-neutron shielded conditions and ∼5.2% under the mixed spectrum condition. Irradiation temperature strongly influences tungsten’s microstructure, with dislocation loops and fine voids forming at lower temperatures and only larger voids and Re /Os segregation observed at higher temperature. Under thermal-neutron shielded conditions, dislocation loops and voids were observed at 570 °C and 790 °C. At the highest irradiation temperature (1130 °C), dislocation loops were no longer observed, while larger but less dense voids remained. Re and Os segregation to void surfaces was evident at 790 °C and 1130 °C, though no precipitation was observed. In contrast, under the mixed-spectrum condition, both spherical and needle-like Re /Os-rich precipitates were observed, frequently accompanied by large voids. Dislocation loops were not observed, but loop-like contrast within the precipitates suggests they may have nucleated on pre-existing loops. Irradiation-induced hardening was assessed for the shielded samples at 570 °C and 790 °C. Dispersed barrier hardening (DBH) analysis, based on TEM-resolved defects, revealed that voids were the dominant contributors to hardening, consistent with literature results. A schematic model is proposed to describe defect and precipitate evolution in tungsten under fusion-relevant transmutation-to-dpa conditions.
| Original language | English |
|---|---|
| Article number | 156697 |
| Journal | Journal of Nuclear Materials |
| Volume | 630 |
| DOIs | |
| State | Published - Aug 2026 |
Funding
This work was supported by the U.S. Department of Energy, Office of Fusion Energy Sciences, Fusion Materials Program under contract DE-AC05-00OR22725 with UT-Battelle, LLC. The work was performed as a part of the U.S.-Japan PHENIX Cooperation Project on Technological Assessment of Plasma Facing Components for DEMO Reactors and the U.S.-Japan FRONTIER collaboration project on fusion research and development, supported by the U.S. Department of Energy, Office of Science, Fusion Energy Sciences and the Ministry of Education, Culture, Sports, Science and Technology, Japan. A portion of this research used resources at the HFIR, a Department of Energy Office of Science User Facility operated by the ORNL. Post irradiation Examination was performed at the Low Activation Materials Development and Analysis (LAMDA) facility, and the authors would like to thank Lauren Garrison and Takaaki Koyanagi (ORNL) for his management of rabbit irradiation, and Patricia Tedder, Kyle Everett, and Sabrina Calzada (ORNL) for their assistant on the sample preparation.
Keywords
- Dislocation loops
- Hardening
- Neutron spectra
- Voids
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