Thermal conductivity degradation and recovery in ion beam damaged tungsten at different temperature

Cui, Shuang; Doerner, R.; Simmonds, M.; Xu, Chuan; Wang, Yongqiang; Dechaumphai, Edward; Fu, Engang; Tynan, G. R.; Chen, Renkun

doi:10.1016/j.jnucmat.2018.09.002

Cited by 26 publications

(15 citation statements)

References 48 publications

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“…For example alloying with transmutation products such as rhenium, tantalum and osmium has been used to study the effects of transmutation [9,11]. Self-ion irradiation is attractive for singling out displacement damage for detailed analysis [12,13].…”

Section: Introductionmentioning

confidence: 99%

Thermal diffusivity degradation and point defect density in self-ion implanted tungsten

Reza

Mizohata

et al. 2020

Acta Materialia

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Section: Introductionmentioning

confidence: 99%

Thermal diffusivity degradation and point defect density in self-ion implanted tungsten

Reza

Mizohata

et al. 2020

Acta Materialia

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“…To distinguish the contributions of the transmutations and the displacements, they performed measurements before and after annealing the sample for 1 h to 10 0 0 • C, and found 28-51% recovery of the thermal conductivity by annealing. Furthermore, Cui et al (2018) measured a 20% reduction of the thermal conductivity at the tungsten surface following 0.2 dpa of ion-irradiation of tungsten at 10 0 0 K, which can be attributed purely to displacement defects.…”

Section: Introductionmentioning

confidence: 94%

“…The effect of neutron displacement damage (such as vacancies, self-interstitial atoms and dislocations) on the thermal material properties of tungsten is often assumed to be negligible ( Barabash, 2013;Tolias & EUROfusion MST1 Team, 2017 ). However, there are convincing indications that the displacement defects lead to a significant decrease in the thermal conductivity: (1) severe cold working of tungsten (wire drawing) was shown to lead to an increase of the electrical resistivity ( Broom, 1952 ) of 50%, and (2) several recent measurements on the thermal diffusivity and thermal conductivity of irradiated tungsten ( Cui et al, 2018;Habainy, Dai, Lee, & Iyengar, 2018 ). Thermal diffusivity measurements by Habainy et al (2018) indicate that the displacement damage significantly affects the thermal conductivity.…”

Section: Introductionmentioning

confidence: 99%

Microstructural evolution and regeneration in neutron-irradiated tungsten monoblocks

Mannheim

Dommelen

Geers

2019

International Journal of Engineering Science

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“…Charged particles accelerated to high energies present an efficient means for the production of displacement damage for a reasonable experimental time period at the levels being of interest for fusion research. This method is widely used in fusionoriented investigations [7][8][9][10][11][12][13][14]. The method has been also taken in our research and it was developed on the basis of experimental facilities at NRC "Kurchatov Institute".…”

Section: Introductionmentioning

confidence: 99%

Thermonuclear Fusion Reactor Plasma-Facing Materials under Conditions of Ion Irradiation and Plasma Flux

2021

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A review of experimental studies carried out at the NRC “Kurchatov Institute” on plasma-facing thermonuclear fusion reactor materials is presented in the paper. An experimental method was developed to produce high-level radiation damage in materials simulating the neutron effect by surrogate irradiation with high-energy ions. Plasma-surface interaction is investigated on materials irradiated to high levels of radiation damage in high-flux deuterium plasma. The total fluence of accelerated ions (3–30 MeV, 4He2+, 12C3+, 14N3+, protons) on the samples was 1021–1023 m−2. Experiments were carried out on graphite materials, tungsten, and silicon carbide. Samples have been obtained with a primary defect concentration from 0.1 to 100 displacements per atom, which covers the predicted damage for the ITER and DEMO projects. Erosion dynamics of the irradiated materials in steady-state deuterium plasma, changes of the surface microstructure, and deuterium retention were studied using SEM, TEM, ERDA, TDS, and nuclear backscattering techniques. The surface layer of the materials (3 to hundreds µm) was investigated, and it was shown that the changes in the crystal structure, the loss of their symmetry, and diffusion of defects to grain boundaries play an important role. The most significant results are presented in the paper as an overview of our previous work for many years (carbon and tungsten materials) as well as the relatively recent results (silicon carbide).

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Thermal conductivity degradation and recovery in ion beam damaged tungsten at different temperature

Cited by 26 publications

References 48 publications

Thermal diffusivity degradation and point defect density in self-ion implanted tungsten

Thermal diffusivity degradation and point defect density in self-ion implanted tungsten

Microstructural evolution and regeneration in neutron-irradiated tungsten monoblocks

Thermonuclear Fusion Reactor Plasma-Facing Materials under Conditions of Ion Irradiation and Plasma Flux

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