Defect evolution in single crystalline tungsten following low temperature and low dose neutron irradiation

Hu, Xunxiang; Koyanagi, Takaaki; Fukuda, Makoto; Katoh, Yutai; Wirth, Brian D; Snead, Lance Lewis

doi:10.1016/j.jnucmat.2015.12.040

Title: Defect evolution in single crystalline tungsten following low temperature and low dose neutron irradiation

Journal Article · Fri Jan 01 00:00:00 EST 2016 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2015.12.040· OSTI ID:1234347

Hu, Xunxiang ^[1]; Koyanagi, Takaaki ^[1]; Fukuda, Makoto ^[2]; Katoh, Yutai ^[1]; Wirth, Brian D ^[3]; Snead, Lance Lewis ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Tohoku Univ., Sendai (Japan)
Univ. of Tennessee, Knoxville, TN (United States)

The tungsten plasma-facing components of fusion reactors will experience an extreme environment including high temperature, intense particle fluxes of gas atoms, high-energy neutron irradiation, and significant cyclic stress loading. Irradiation-induced defect accumulation resulting in severe thermo-mechanical property degradation is expected. For this reason, and because of the lack of relevant fusion neutron sources, the fundamentals of tungsten radiation damage must be understood through coordinated mixed-spectrum fission reactor irradiation experiments and modeling. In this study, high-purity (110) single-crystal tungsten was examined by positron annihilation spectroscopy and transmission electron microscopy following low-temperature (~90 °C) and low-dose (0.006 and 0.03 dpa) mixed-spectrum neutron irradiation and subsequent isochronal annealing at 400, 500, 650, 800, 1000, 1150, and 1300 °C. The results provide insights into microstructural and defect evolution, thus identifying the mechanisms of different annealing behavior. Following 1 h annealing, ex situ characterization of vacancy defects using positron lifetime spectroscopy and coincidence Doppler broadening was performed. The vacancy cluster size distributions indicated intense vacancy clustering at 400 °C with significant damage recovery around 1000 °C. Coincidence Doppler broadening measurements confirm the trend of the vacancy defect evolution, and the S–W plots indicate that only a single type of vacancy cluster is present. Furthermore, transmission electron microscopy observations at selected annealing conditions provide supplemental information on dislocation loop populations and visible void formation. This microstructural information is consistent with the measured irradiation-induced hardening at each annealing stage. This provides insight into tungsten hardening and embrittlement due to irradiation-induced matrix defects.

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Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). High Flux Isotope Reactor (HFIR)

Sponsoring Organization:: USDOE Laboratory Directed Research and Development (LDRD) Program; USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: AC05-00OR22725; DOE-DE-SC0006661

OSTI ID:: 1234347

Alternate ID(s):: OSTI ID: 1252047

Journal Information:: Journal of Nuclear Materials, Vol. 470; ISSN 0022-3115

Country of Publication:: United States

Language:: English

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Cited by: 85 works

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