Deuterium and helium ion irradiation of nanograined tungsten and tungsten–titanium alloys

L. Buzi; M. Yeh; Y. W. Yeh; O. K. Donaldson; M. I. Patino; J. R. Trelewicz; N. Yao; R. Doerner; B. E. Koel

doi:10.1016/j.nme.2019.100713

Deuterium and helium ion irradiation of nanograined tungsten and tungsten–titanium alloys

L. Buzi, M. Yeh, Y. W. Yeh, O. K. Donaldson, M. I. Patino, J. R. Trelewicz, N. Yao, R. Doerner, B. E. Koel

Research output: Contribution to journal › Article › peer-review

14 Scopus citations

Abstract

Tungsten (W), a primary candidate for the plasma-facing components of nuclear fusion reactors (e.g. the divertor region in ITER) is susceptible to cracks, blisters, bubbles, and other morphological changes when irradiated with energetic particles. This work investigated two new materials, nanograined W and a nanograined W–Ti alloy, for potential use as plasma-facing materials. Their retention properties and morphological changes after exposure to deuterium (D) and helium (He) plasma at 50 eV and surface temperatures of 500 and 1000 K were analyzed. Nanograined W was found to have smaller blisters and be less prone to fuzz formation than commonly-utilized micro-grain polycrystalline W. Additionally, the nanograined W–Ti alloy exhibited a lower concentration of blisters on its surface than pure W, including nanograined W.

Original language	English (US)
Article number	100713
Journal	Nuclear Materials and Energy
Volume	21
DOIs	https://doi.org/10.1016/j.nme.2019.100713
State	Published - Dec 2019

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Nuclear Energy and Engineering
Materials Science (miscellaneous)

Keywords

Deuterium
Helium
Plasma-facing materials
Tungsten

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10.1016/j.nme.2019.100713

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title = "Deuterium and helium ion irradiation of nanograined tungsten and tungsten–titanium alloys",

abstract = "Tungsten (W), a primary candidate for the plasma-facing components of nuclear fusion reactors (e.g. the divertor region in ITER) is susceptible to cracks, blisters, bubbles, and other morphological changes when irradiated with energetic particles. This work investigated two new materials, nanograined W and a nanograined W–Ti alloy, for potential use as plasma-facing materials. Their retention properties and morphological changes after exposure to deuterium (D) and helium (He) plasma at 50 eV and surface temperatures of 500 and 1000 K were analyzed. Nanograined W was found to have smaller blisters and be less prone to fuzz formation than commonly-utilized micro-grain polycrystalline W. Additionally, the nanograined W–Ti alloy exhibited a lower concentration of blisters on its surface than pure W, including nanograined W.",

keywords = "Deuterium, Helium, Plasma-facing materials, Tungsten",

author = "L. Buzi and M. Yeh and Yeh, {Y. W.} and Donaldson, {O. K.} and Patino, {M. I.} and Trelewicz, {J. R.} and N. Yao and R. Doerner and Koel, {B. E.}",

note = "Publisher Copyright: {\textcopyright} 2019 The Authors",

year = "2019",

month = dec,

doi = "10.1016/j.nme.2019.100713",

language = "English (US)",

volume = "21",

journal = "Nuclear Materials and Energy",

issn = "2352-1791",

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TY - JOUR

T1 - Deuterium and helium ion irradiation of nanograined tungsten and tungsten–titanium alloys

AU - Buzi, L.

AU - Yeh, M.

AU - Yeh, Y. W.

AU - Donaldson, O. K.

AU - Patino, M. I.

AU - Trelewicz, J. R.

AU - Yao, N.

AU - Doerner, R.

AU - Koel, B. E.

PY - 2019/12

Y1 - 2019/12

N2 - Tungsten (W), a primary candidate for the plasma-facing components of nuclear fusion reactors (e.g. the divertor region in ITER) is susceptible to cracks, blisters, bubbles, and other morphological changes when irradiated with energetic particles. This work investigated two new materials, nanograined W and a nanograined W–Ti alloy, for potential use as plasma-facing materials. Their retention properties and morphological changes after exposure to deuterium (D) and helium (He) plasma at 50 eV and surface temperatures of 500 and 1000 K were analyzed. Nanograined W was found to have smaller blisters and be less prone to fuzz formation than commonly-utilized micro-grain polycrystalline W. Additionally, the nanograined W–Ti alloy exhibited a lower concentration of blisters on its surface than pure W, including nanograined W.

AB - Tungsten (W), a primary candidate for the plasma-facing components of nuclear fusion reactors (e.g. the divertor region in ITER) is susceptible to cracks, blisters, bubbles, and other morphological changes when irradiated with energetic particles. This work investigated two new materials, nanograined W and a nanograined W–Ti alloy, for potential use as plasma-facing materials. Their retention properties and morphological changes after exposure to deuterium (D) and helium (He) plasma at 50 eV and surface temperatures of 500 and 1000 K were analyzed. Nanograined W was found to have smaller blisters and be less prone to fuzz formation than commonly-utilized micro-grain polycrystalline W. Additionally, the nanograined W–Ti alloy exhibited a lower concentration of blisters on its surface than pure W, including nanograined W.

KW - Deuterium

KW - Helium

KW - Plasma-facing materials

KW - Tungsten

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DO - 10.1016/j.nme.2019.100713

M3 - Article

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SN - 2352-1791

VL - 21

JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

M1 - 100713

ER -

Deuterium and helium ion irradiation of nanograined tungsten and tungsten–titanium alloys

Abstract

All Science Journal Classification (ASJC) codes

Keywords

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