Defect Production, Evolution, and Thermal Recovery Mechanisms in Radiation Damaged Tungsten

doi:10.11900/0412.1961.2020.00228

Acta Metall Sin

2021, Vol. 57

Issue (3): 257-271 DOI: 10.11900/0412.1961.2020.00228

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Defect Production, Evolution, and Thermal Recovery Mechanisms in Radiation Damaged Tungsten

YI Xiaoou¹(

), HAN Wentuo¹, LIU Pingping¹, FERRONI Francesco², ZHAN Qian¹, WAN Farong¹

^1.School of Materials Science and Engineering, University of Science and Technology Beijing, Beijing 100083, China
^2.Department of Materials, University of Oxford, Oxford OX1 3PH, U. K.

Cite this article:

YI Xiaoou, HAN Wentuo, LIU Pingping, FERRONI Francesco, ZHAN Qian, WAN Farong. Defect Production, Evolution, and Thermal Recovery Mechanisms in Radiation Damaged Tungsten. Acta Metall Sin, 2021, 57(3): 257-271.

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Abstract

Tungsten (W) is a prime candidate for use in plasma-facing components in fusion reactors. These components are subjected to high temperatures and displacement damages caused by fusion neutron bombardments. The displacement damages are mainly present as high concentrations of point defects and clusters. They interact with the hydrogen, helium plasma, and various other transmutation products, giving rise to unwanted consequences, such as radiation hardening, increased brittle-to-ductile transition temperature, and thermal conductivity degradation. This review focuses on the radiation-induced displacement damage in tungsten and aims to provide a systematic summary of the underlying mechanisms for the production, evolution, and thermal recovery of radiation defect, using defect microscopy techniques and materials multiscale modeling. The information uncovered, reflects statistical laws of radiation defect characteristics; serves as the basis for a quantitative description of time- and space-dependent evolution of damage microstructure; and is in great favor of material property prediction, reliability evaluation, and the future development of novel materials.

Key words: fusion reactor W radiation defect production evolution thermal recovery

Received: 30 June 2020

ZTFLH:

TG146.4

Fund: National Natural Science Foundation of China(51701014)

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	Xiaoou YI
	Wentuo HAN
	Pingping LIU
	Francesco FERRONI
	Qian ZHAN
	Farong WAN

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https://www.ams.org.cn/EN/10.11900/0412.1961.2020.00228 OR https://www.ams.org.cn/EN/Y2021/V57/I3/257

Fig.1 Spatial distribution analysis of radiation defects in individual collision cascades of tungsten^[55]

Fig.2 Evolution behaviour of radiation defects^[47]

Fig.3 Dose rate effect upon radiation defect densities (loops or voids) in tungsten (Neutron irradiations: HFIR, 0.6 dpa, 363-997 K^[86]; JOYO, 0.17-0.44 dpa, 804-1029 K^[14,85]; ion irradiation: 2 MeV W⁺, 0.4 dpa, 573-773 K and 1.2 dpa, 1023 K^[76])

Fig.4 Evolution of damage structure in 2 MeV W⁺ ion irradiated tungsten (773 K, 1.5 dpa) during dynamic annealing from room temperature (R.T.) to 1473 K (a-h) (Imaging condition: two-beam kinematical bright-field, g=_{0 $2 ˉ$ 0)^[119]}

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