A study of the effect of helium concentration and displacement damage on the microstructure of helium ion irradiated tungsten

Research output: Contribution to journalArticle

16 Citations (Scopus)

Abstract

Transmission electron microscopy (TEM) with in situ He ion irradiation has been used to examine the damage microstructure of W when varying the helium concentration to displacement damage ratio, irradiation temperature and total dose. Irradiations employed 15, 60 or 85 keV He+ ions, at temperatures between 500 and 1000 °C up to doses of ∼3.0 DPA. Once nucleated and grown to an observable size in the TEM, bubble diameter as a function of irradiation dose did not measurably increase at irradiation temperatures of 500 °C between 1.0 and 3.0 DPA; this is attributed to the low mobility of vacancies and He/vacancy complexes at these temperatures. Bubble diameter increased slightly for irradiation temperatures of 750 °C and rapidly increased when irradiated at 1000 °C. Dislocation loops were observed for at irradiation temperature of 500 and 750 °C and no loops were observed at 1000 °C. Burgers vectors of the dislocations were determined to be b = ±1/2<111> type only and both vacancy and interstitial loops were observed. The proportion of interstitial loops increased with He-appm/DPA ratio and this is attributed to the concomitant increase in bubble areal density, which reduces the vacancy flux for both the growth of vacancy-type loops and the annihilation of interstitial clusters.
LanguageEnglish
Pages492-503
Number of pages12
JournalJournal of Nuclear Materials
Volume495
Early online date30 Aug 2017
DOIs
Publication statusPublished - Nov 2017

Fingerprint

Helium
Tungsten
helium ions
tungsten
Vacancies
helium
Irradiation
Ions
damage
microstructure
Microstructure
irradiation
interstitials
bubbles
dosage
Temperature
Dosimetry
temperature
Transmission electron microscopy
Burgers vector

Cite this

@article{3077e0ac1698412f952b274abc7b1301,
title = "A study of the effect of helium concentration and displacement damage on the microstructure of helium ion irradiated tungsten",
abstract = "Transmission electron microscopy (TEM) with in situ He ion irradiation has been used to examine the damage microstructure of W when varying the helium concentration to displacement damage ratio, irradiation temperature and total dose. Irradiations employed 15, 60 or 85 keV He+ ions, at temperatures between 500 and 1000 °C up to doses of ∼3.0 DPA. Once nucleated and grown to an observable size in the TEM, bubble diameter as a function of irradiation dose did not measurably increase at irradiation temperatures of 500 °C between 1.0 and 3.0 DPA; this is attributed to the low mobility of vacancies and He/vacancy complexes at these temperatures. Bubble diameter increased slightly for irradiation temperatures of 750 °C and rapidly increased when irradiated at 1000 °C. Dislocation loops were observed for at irradiation temperature of 500 and 750 °C and no loops were observed at 1000 °C. Burgers vectors of the dislocations were determined to be b = ±1/2<111> type only and both vacancy and interstitial loops were observed. The proportion of interstitial loops increased with He-appm/DPA ratio and this is attributed to the concomitant increase in bubble areal density, which reduces the vacancy flux for both the growth of vacancy-type loops and the annihilation of interstitial clusters.",
keywords = "Tungsten, Irradiation, Fusion, Radiation damage, In situ TEM",
author = "Harrison, {R. W.} and G. Greaves and Hinks, {J. A.} and Donnelly, {S. E.}",
year = "2017",
month = "11",
doi = "10.1016/j.jnucmat.2017.08.033",
language = "English",
volume = "495",
pages = "492--503",
journal = "Journal of Nuclear Materials",
issn = "0022-3115",
publisher = "Elsevier",

}

TY - JOUR

T1 - A study of the effect of helium concentration and displacement damage on the microstructure of helium ion irradiated tungsten

AU - Harrison, R. W.

AU - Greaves, G.

AU - Hinks, J. A.

AU - Donnelly, S. E.

PY - 2017/11

Y1 - 2017/11

N2 - Transmission electron microscopy (TEM) with in situ He ion irradiation has been used to examine the damage microstructure of W when varying the helium concentration to displacement damage ratio, irradiation temperature and total dose. Irradiations employed 15, 60 or 85 keV He+ ions, at temperatures between 500 and 1000 °C up to doses of ∼3.0 DPA. Once nucleated and grown to an observable size in the TEM, bubble diameter as a function of irradiation dose did not measurably increase at irradiation temperatures of 500 °C between 1.0 and 3.0 DPA; this is attributed to the low mobility of vacancies and He/vacancy complexes at these temperatures. Bubble diameter increased slightly for irradiation temperatures of 750 °C and rapidly increased when irradiated at 1000 °C. Dislocation loops were observed for at irradiation temperature of 500 and 750 °C and no loops were observed at 1000 °C. Burgers vectors of the dislocations were determined to be b = ±1/2<111> type only and both vacancy and interstitial loops were observed. The proportion of interstitial loops increased with He-appm/DPA ratio and this is attributed to the concomitant increase in bubble areal density, which reduces the vacancy flux for both the growth of vacancy-type loops and the annihilation of interstitial clusters.

AB - Transmission electron microscopy (TEM) with in situ He ion irradiation has been used to examine the damage microstructure of W when varying the helium concentration to displacement damage ratio, irradiation temperature and total dose. Irradiations employed 15, 60 or 85 keV He+ ions, at temperatures between 500 and 1000 °C up to doses of ∼3.0 DPA. Once nucleated and grown to an observable size in the TEM, bubble diameter as a function of irradiation dose did not measurably increase at irradiation temperatures of 500 °C between 1.0 and 3.0 DPA; this is attributed to the low mobility of vacancies and He/vacancy complexes at these temperatures. Bubble diameter increased slightly for irradiation temperatures of 750 °C and rapidly increased when irradiated at 1000 °C. Dislocation loops were observed for at irradiation temperature of 500 and 750 °C and no loops were observed at 1000 °C. Burgers vectors of the dislocations were determined to be b = ±1/2<111> type only and both vacancy and interstitial loops were observed. The proportion of interstitial loops increased with He-appm/DPA ratio and this is attributed to the concomitant increase in bubble areal density, which reduces the vacancy flux for both the growth of vacancy-type loops and the annihilation of interstitial clusters.

KW - Tungsten

KW - Irradiation

KW - Fusion

KW - Radiation damage

KW - In situ TEM

UR - https://www.journals.elsevier.com/journal-of-nuclear-materials

U2 - 10.1016/j.jnucmat.2017.08.033

DO - 10.1016/j.jnucmat.2017.08.033

M3 - Article

VL - 495

SP - 492

EP - 503

JO - Journal of Nuclear Materials

T2 - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

ER -