skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: A study on the sintering of ultrafine grained tungsten with Ti-based additives

Authors:
; ; ; ;
Publication Date:
Sponsoring Org.:
USDOE
OSTI Identifier:
1398082
Grant/Contract Number:
DESC0008673
Resource Type:
Journal Article: Publisher's Accepted Manuscript
Journal Name:
International Journal of Refractory and Hard Metals
Additional Journal Information:
Journal Volume: 65; Journal Issue: C; Related Information: CHORUS Timestamp: 2017-10-05 09:06:43; Journal ID: ISSN 0263-4368
Publisher:
Elsevier
Country of Publication:
United Kingdom
Language:
English

Citation Formats

Ren, Chai, Koopman, Mark, Zak Fang, Z., Zhang, Huan, and van Devener, Brian. A study on the sintering of ultrafine grained tungsten with Ti-based additives. United Kingdom: N. p., 2017. Web. doi:10.1016/j.ijrmhm.2016.11.013.
Ren, Chai, Koopman, Mark, Zak Fang, Z., Zhang, Huan, & van Devener, Brian. A study on the sintering of ultrafine grained tungsten with Ti-based additives. United Kingdom. doi:10.1016/j.ijrmhm.2016.11.013.
Ren, Chai, Koopman, Mark, Zak Fang, Z., Zhang, Huan, and van Devener, Brian. 2017. "A study on the sintering of ultrafine grained tungsten with Ti-based additives". United Kingdom. doi:10.1016/j.ijrmhm.2016.11.013.
@article{osti_1398082,
title = {A study on the sintering of ultrafine grained tungsten with Ti-based additives},
author = {Ren, Chai and Koopman, Mark and Zak Fang, Z. and Zhang, Huan and van Devener, Brian},
abstractNote = {},
doi = {10.1016/j.ijrmhm.2016.11.013},
journal = {International Journal of Refractory and Hard Metals},
number = C,
volume = 65,
place = {United Kingdom},
year = 2017,
month = 6
}

Journal Article:
Free Publicly Available Full Text
This content will become publicly available on March 19, 2018
Publisher's Accepted Manuscript

Save / Share:
  • Abstract not provided.
  • Abstract not provided.
  • Plasma facing components for future fusion applications will experience helium- and neutron-induced structural damage. Direct observation of the in-situ dynamic response of such components during particle beam exposure assists in fundamental understanding of the physical phenomena that give rise to their irradiation resistance. We investigated the response of ultrafine and nanocrystalline-grained tungsten to 3 MeV heavy ion irradiations (Si{sup 2} {sup +}, Cu{sup 3} {sup +} and W{sup 4} {sup +}) for the simulation of neutron-induced damage through transmutation reactions via in-situ ion irradiation–transmission electron microscopy experiments. Defect densities as a function of irradiation dose (displacement per atom) and fluencemore » were studied. Four stages of defect densities evolution were observed, as a function of irradiation dose: 1) increase in defect density at lower doses, 2) higher defect production rate at the intermediate doses (before saturation), 3) reaching the maximum value, and 4) drop of the defect density in the case of W{sup 4} {sup +}, possibly due to defect coalescence and grain boundary absorption of small defect clusters. The effect of grain size on defect densities was investigated and found that defect densities were independent of grain size in the ultrafine and nanocrystalline region (60–400 nm). These results were compared to other heavy ion irradiation studies of structural materials. - Graphical abstract: Bright-field TEM micrographs and defect densities of UF and NC tungsten grains irradiated with a) Si{sup +} {sup 2} at 1.03 dpa: 1) 140 nm — 7.2 × 10{sup −} {sup 3} defects/nm{sup 2}, 2) 122 nm — 6.9 × 10{sup −} {sup 3} defects/nm{sup 2}, 3) 63 nm — 4.7 × 10{sup −} {sup 3} defects/nm{sup 2}, and 4) 367 nm — 6.4 × 10{sup −} {sup 3} defects/nm{sup 2}; b) Cu{sup +} {sup 3} to 3.79 dpa: 1) 228 nm — 4.3 × 10{sup −} {sup 3} defects/nm{sup 2}; 2) 202 nm — 5.9 × 10{sup −} {sup 3} defects/nm{sup 2}; and 3) 137 nm — 6.1 × 10{sup −} {sup 3} defects/nm{sup 2}; and c) W{sup +} {sup 4} to 5.72 dpa: 1) 372 nm — 2.3 × 10{sup −} {sup 3} defects/nm{sup 2} and 2) 128 nm — 4.5 × 10{sup −} {sup 3} defects/nm{sup 2}. - Highlights: • Heavy ion irradiations were performed on UF and NC grained tungsten. • Irradiations were performed with 3 MeV (Si{sup 2} {sup +}, Cu{sup 3} {sup +} and W{sup 4} {sup +}) ions at RT. • Defect density vs. dpa demonstrated four different stages in the case of W{sup 4} {sup +} irradiation. • Defect coalescence and absorption by the grain boundaries were observed after a dose of 3 dpa during W{sup 4} {sup +} irradiation. • No correlation existed between the grain width and the defect density for the UF and NC region.« less