This content will become publicly available on Thu Jun 13 00:00:00 EDT 2024
Degradation of electrical resistivity of tungsten following shielded neutron irradiation
Abstract
A major challenge for heat transfer in nuclear materials is to ensure thermal mobility after high amounts of neutron irradiation. Tungsten is widely selected as a heat transfer material in fusion reactors. In metals, thermal conductivity is dominated by electrons’ ability to transfer energy. Neutron irradiation generates point defects, clusters, and solid transmutation (e.g.rhenium and osmium in tungsten), which inhibit electron motion. The purpose of this work is to quantify the irradiation-induced change in electron mobility and deconvolute transmutation and microstructural effects on observed changes to electron mobility. Single and polycrystalline tungsten were fast neutron irradiated in the High Flux Isotope Reactor at Oak Ridge National Laboratory to doses between 0.2 and 0.7 displacements per atom (dpa) and temperatures from 500 °C to 1000 °C. Grain growth was observed in all samples. Microstructure and transmutation were quantified. The geometric orientation of samples with elongated grains has been shown to affect electrical resistivity. A mathematical model was developed and used to deconvolute solid-solution transmutation, grain, and temperature-dependent lattice effects on resistivity. At ~0.4 dpa at ~590 °C, the combined resistivity degradation due to voids, vacancies, interstitials, and dislocations is estimated to be greater than the contribution from solid solution Re transmutation,more »
- Authors:
-
[1];
[2];
[3];
[4];
[5];
[1];
[4];
[6];
[4];
[4]
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); UK Atomic Energy Authority (UKAEA), Culham (United Kingdom)
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Commonwealth Fusion Systems, Devens, MA (United States)
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); University of Illinois at Urbana-Champaign, IL (United States)
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Tohoku University, Sendai (Japan)
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Savannah River National Laboratory (SRNL), Aiken, SC (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE Office of Science (SC), Basic Energy Sciences (BES). Scientific User Facilities (SUF)
- OSTI Identifier:
- 1995719
- Alternate Identifier(s):
- OSTI ID: 2000137
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Acta Materialia
- Additional Journal Information:
- Journal Volume: 257; Journal ID: ISSN 1359-6454
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; Tungsten; Grain boundaries; Transport properties; EBSD; Neutron irradiation
Citation Formats
Echols, John R., Garrison, Lauren M., Reid, Nathan, Parish, Chad M., Hasegawa, Akira, Bhattacharya, Arunodaya, Zhong, Weicheng, Morrall, Daniel, Lance, Michael J., and Katoh, Yutai. Degradation of electrical resistivity of tungsten following shielded neutron irradiation. United States: N. p., 2023.
Web. doi:10.1016/j.actamat.2023.119025.
Echols, John R., Garrison, Lauren M., Reid, Nathan, Parish, Chad M., Hasegawa, Akira, Bhattacharya, Arunodaya, Zhong, Weicheng, Morrall, Daniel, Lance, Michael J., & Katoh, Yutai. Degradation of electrical resistivity of tungsten following shielded neutron irradiation. United States. https://doi.org/10.1016/j.actamat.2023.119025
Echols, John R., Garrison, Lauren M., Reid, Nathan, Parish, Chad M., Hasegawa, Akira, Bhattacharya, Arunodaya, Zhong, Weicheng, Morrall, Daniel, Lance, Michael J., and Katoh, Yutai. Tue .
"Degradation of electrical resistivity of tungsten following shielded neutron irradiation". United States. https://doi.org/10.1016/j.actamat.2023.119025.
@article{osti_1995719,
title = {Degradation of electrical resistivity of tungsten following shielded neutron irradiation},
author = {Echols, John R. and Garrison, Lauren M. and Reid, Nathan and Parish, Chad M. and Hasegawa, Akira and Bhattacharya, Arunodaya and Zhong, Weicheng and Morrall, Daniel and Lance, Michael J. and Katoh, Yutai},
abstractNote = {A major challenge for heat transfer in nuclear materials is to ensure thermal mobility after high amounts of neutron irradiation. Tungsten is widely selected as a heat transfer material in fusion reactors. In metals, thermal conductivity is dominated by electrons’ ability to transfer energy. Neutron irradiation generates point defects, clusters, and solid transmutation (e.g.rhenium and osmium in tungsten), which inhibit electron motion. The purpose of this work is to quantify the irradiation-induced change in electron mobility and deconvolute transmutation and microstructural effects on observed changes to electron mobility. Single and polycrystalline tungsten were fast neutron irradiated in the High Flux Isotope Reactor at Oak Ridge National Laboratory to doses between 0.2 and 0.7 displacements per atom (dpa) and temperatures from 500 °C to 1000 °C. Grain growth was observed in all samples. Microstructure and transmutation were quantified. The geometric orientation of samples with elongated grains has been shown to affect electrical resistivity. A mathematical model was developed and used to deconvolute solid-solution transmutation, grain, and temperature-dependent lattice effects on resistivity. At ~0.4 dpa at ~590 °C, the combined resistivity degradation due to voids, vacancies, interstitials, and dislocations is estimated to be greater than the contribution from solid solution Re transmutation, which is greater than the contribution from grain boundaries. At doses of ~0.7 dpa at ~750 °C, solid solution Re contributions are greater than all other effects combined. As a result, this work establishes a basis to predict the effects of irradiation temperature and transmutation on thermal properties of tungsten and highlights the importance of irradiation temperature.},
doi = {10.1016/j.actamat.2023.119025},
journal = {Acta Materialia},
number = ,
volume = 257,
place = {United States},
year = {Tue Jun 13 00:00:00 EDT 2023},
month = {Tue Jun 13 00:00:00 EDT 2023}
}
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