Published March 2019 | Version v1
Journal article

Combined effect of laser thermal shock and helium ion irradiation on W-Y2O3 composites

  • 1. School of Materials Science and Engineering, Hefei University of Technology, Hefei 230009 (China)
  • 2. Laboratory of Nonferrous Metal Material and Processing Engineering of Anhui Province, Hefei 230009 (China)
  • 3. Institute for Integrated Radiation and Nuclear Science, Kyoto University, Osaka-fu 590-0494 (Japan)
  • 4. Research Institute for Applied Mechanics, Kyushu University, Kasuga, Fukuoka 816-8580 (Japan)
  • 5. National-Local Joint Engineering Research Centre of Nonferrous Metals and Processing Technology, Hefei 230009 (China)

Description

Highlights: • Thermal shock behavior of samples was characterized after helium irradiation. • Combined helium irradiation and thermal shock has significant influence on crack propagation. • Observing fuzz was more likely to converge densely at the phase interface. • Y2O3 doping can improve thermal shock resistance of the W-Y2O3 composite. -- Abstract: Tungsten can be the preferred plasma-facing material for nuclear fusion reaction. In this work, W-Y2O3 composite powder was successfully fabricated through the wet chemical method, and bulk materials were obtained by rolling and high temperature annealing. W-2 vol% Y2O3 was exposed to 80 eV helium ion irradiation with a flux of 1.5 × 1022 ions/(m2·s) at 1503–1553 K to assess its thermal shock resistance and helium ion irradiation damage behavior. The thermal shock behaviors of samples were studied under a laser beam. The energy densities of the laser thermal shock were 0.32, 0.48, and 0.64 GW/m2. W-Y2O3 was compared with commercial pure tungsten. The hardness of pure tungsten and W-Y2O3 before and after helium irradiation was measured by using a micro-hardness tester. The surface micrograph after helium ion irradiation and thermal shock was observed through scanning electron microscopy. Results show that W-Y2O3 composite materials have better resistance to laser thermal shock than pure tungsten.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2019.01.134

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2019.01.134;
PII
S0920379619301528;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
140
Journal Page Range
p. 102-106
ISSN
0920-3796
CODEN
FEDEEE

Optional Information

Copyright
Copyright (c) 2019 Elsevier B.V. All rights reserved.