不同辐照粒子下钨及钨合金辐照损伤行为的研究进展

doi:10.11896/j.issn.1005-023X.2018.01.004

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Abstract

It is difficult and urgent task to develop a high-performance plasma facing materials for current nuclear fusion research by the irradiation behavior of PFMs, which is suitable for advanced experiment superconducting tokamak (EAST), international thermonuclear fusion reactor (ITER) and China fusion engineering experiment reactor (CFETR). Tungsten is considered to be the primary candidate for plasma facing materials in future fusion reactors owing to its superiority to other materials including high melting point, high thermal conductivity, low sputter corrosion rate, high sputtering threshold, low vapor pressure and low tritium inventory. In this paper, we review the research progress of damage of tungsten and tungsten alloy irradiated by various particles. The defects caused by irradiation are accumulate in tungsten and tungsten alloy. The formation and quantity of defects are closely related to the microstructure of the tungsten and the second phase components, the situation of defects are diverse. At the same time, the irradiation conditions, for instance, the kinds of particles, energy, flux and temperature, will also have an important impact on the morphology and defect of the irradiated sample.

Key words： tungsten nuclear fusion reactor radiation damage plasma facing materials

Published: 10 January 2018 Online: 2018-01-10

CLC number:

TG146.4

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	Articles by authors
	Laima LUO
	Mengyao XU
	Xiang ZAN
	Xiaoyong ZHU
	Ping LI
	Jigui CHENG
	Yucheng WU

Cite this article:

Laima LUO,Mengyao XU,Xiang ZAN, et al. Progress in Irradiation Damage of Tungsten and Tungsten AlloysUnder Different Irradiation Particles[J]. Materials Reports, 2018, 32(1): 41-46.

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https://www.mater-rep.com/EN/10.11896/j.issn.1005-023X.2018.01.004 OR https://www.mater-rep.com/EN/Y2018/V32/I1/41

The suffered irradiation PFM in fusion reactors^[6]

TEM micrographs of the irradiated ultrafine-grainedtungsten sample:(a) several rod-shape nanostructures,(b) high resolution image of a rod-shape nanostructure,(c) region of bubbles in between two rod-shape nanostructures,(d) region of ~10 nm below the sample surface

Cross-sectional SEM images of W specimens irradiatedwith different He⁺ fluxes:(a) 2.3 × 10²¹/(m²·s),(b) 5.4×10²¹/(m²·s),(c) 7.7×10²¹/(m²·s),(d) 1.0×10²²/(m²·s),(e) 1.3×10²²/(m²·s),(f) 1.6×10²²/(m²·s)

Surface morphology of samples post-irradiated bymixed H⁺-C⁺ beam:(a) undamaged,(b) damaged by300 keV H^-,(c) damaged by 700 keV H^-

TEM images of unirradiated specimens:(a) pure W,(b) La-doped W,(c) K-doped W,(d) UFG W-0.5TiC/H

TEM images of irradiated specimens:(a) pure W,(b) La-doped W,(c) K-doped W,(d) UFG W-0.5 TiC/H

HRTEM images of tungsten after irradiation:(a) grainwith both α and β phase,(b) coarsened grain with α phaseafter 30 dpa irradiation,(c,d) vacancy of the interior regionof coarsened grain,(e) 100 dpa irradiation

STEM bright field damaged zone image of the0.89 dpa damaged sample

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