Thermal diffusivity of irradiated tungsten and tungsten-rhenium alloys
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. Furthermore, 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.
- Authors:
-
[2];
[2];
[2]
- Osaka Prefecture Univ., Sakai (Japan)
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Tohoku Univ., Sendai (Japan)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC), Fusion Energy Sciences (FES)
- OSTI Identifier:
- 1777707
- Alternate Identifier(s):
- OSTI ID: 1776034
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Volume: 543; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; Thermal diffusivity; tungsten material; neutron irradiation; transmutation; lattice defect
Citation Formats
Akiyoshi, Masafumi, Garrison, Lauren M., Geringer, Josina W., Wang, Hsin, Hasegawa, Akira, Nogami, Shuhei, and Katoh, Yutai. Thermal diffusivity of irradiated tungsten and tungsten-rhenium alloys. United States: N. p., 2020.
Web. doi:10.1016/j.jnucmat.2020.152594.
Akiyoshi, Masafumi, Garrison, Lauren M., Geringer, Josina W., Wang, Hsin, Hasegawa, Akira, Nogami, Shuhei, & Katoh, Yutai. Thermal diffusivity of irradiated tungsten and tungsten-rhenium alloys. United States. https://doi.org/10.1016/j.jnucmat.2020.152594
Akiyoshi, Masafumi, Garrison, Lauren M., Geringer, Josina W., Wang, Hsin, Hasegawa, Akira, Nogami, Shuhei, and Katoh, Yutai. Thu .
"Thermal diffusivity of irradiated tungsten and tungsten-rhenium alloys". United States. https://doi.org/10.1016/j.jnucmat.2020.152594. https://www.osti.gov/servlets/purl/1777707.
@article{osti_1777707,
title = {Thermal diffusivity of irradiated tungsten and tungsten-rhenium alloys},
author = {Akiyoshi, Masafumi and Garrison, Lauren M. and Geringer, Josina W. and Wang, Hsin and Hasegawa, Akira and Nogami, Shuhei and Katoh, Yutai},
abstractNote = {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. Furthermore, 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.},
doi = {10.1016/j.jnucmat.2020.152594},
journal = {Journal of Nuclear Materials},
number = ,
volume = 543,
place = {United States},
year = {Thu Oct 15 00:00:00 EDT 2020},
month = {Thu Oct 15 00:00:00 EDT 2020}
}
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