Abstract
The Japan-US PHENIX project irradiated tungsten materials in the RB-19J capsule experiment in the High Flux Isotope Reactor (HFIR). A gadolinium (Gd) shielding was used to absorb the thermal neutrons and reduce rhenium and osmium generation in tungsten. Pure tungsten and K-doped W-3% Re samples were irradiated at 532 – 662 °C to dose of 0.21-0.46 dpa, with the grain orientation perpendicular or parallel to the disk surface. Thermal diffusivity measurements were performed from 100 °C to 500 °C. Additional measurements followed after annealing up to 900 °C. Irradiated pure tungsten specimens showed similar thermal diffusivity results compared with an unirradiated W-1% Re specimen in another study. The transmutation amount of Re was calculated to be about 0.52% for those specimens that showed good agreement with this study. Specimens irradiated in this study to different doses presented almost the same thermal diffusivity. Annealing up to 800 °C resulted in no recovery of thermal diffusivity. These results show that the contribution of crystalline defects to degradation of thermal diffusivity is quite limited. In addition, the thermal diffusivity of the irradiated specimens was getting close to that of the unirradiated specimens at elevated temperature.
Original language | English |
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Article number | 152594 |
Journal | Journal of Nuclear Materials |
Volume | 543 |
DOIs | |
State | Published - Jan 2021 |
Funding
This work was performed as part of the U.S.-Japan PHENIX Cooperation Collaboration Project on Technological Assessment of Plasma Facing Components for DEMO Reactors, supported by the U.S. Department of Energy, Office of Science, Fusion Energy Sciences and Ministry of Education, Culture, Sports, Science and Technology, Japan. ORNL research sponsored by the U.S. Department of Energy , Office of Fusion Energy Sciences, under contract DE-AC05-00OR22725 with UT-Battelle, LLC.
Keywords
- Lattice defect
- Neutron irradiation
- Thermal diffusivity
- Transmutation
- Tungsten material