TY - JOUR
T1 - TEM investigation of helium bubble evolution in tungsten and ZrC-strengthened tungsten at 800 and 1000°C under 40keV He+ irradiation
AU - Ipatova, Iuliia
AU - Greaves, Grame
AU - Terentyev, Dmitry
AU - Gilbert, M. R.
AU - Chiu, Y. L.
N1 - Score=10
Funding Information:
The authors of this work acknowledge Prof S. E. Donnelly for access to the MIAMI-2 facility (grant ref. EPSRC EP/M028283/1 ) through the EPSRC-funded mid-range facility , the UK National Ion Beam Centre ( NS/A000059/1 ). This work has been part-funded by the EPSRC Energy Programme [grant number EP/W006839/1 ]. The authors acknowledge Prof Yu Lung Chiu and the Centre for Electron Microscopy at the University of Birmingham for the provided support and assistance.
Publisher Copyright:
© 2023 Korean Nuclear Society
PY - 2024/4
Y1 - 2024/4
N2 - Helium-induced defect nucleation and accumulation in polycrystalline W and W0.5 wt%ZrC (W0.5ZrC) were studied in-situ using the transmission electron microscopy (TEM) combined with 40 keV He+ irradiation at 800 and 1000°С at the maximum damage level of 1 dpa. Radiation-induced dislocation loops were not observed in the current study. W0.5ZrC was found to be less susceptible to irradiation damage in terms of helium bubble formation and growth, especially at lower temperature (800 °C) when vacancies were less mobile. The ZrC particles present in the W matrix pin the forming helium bubbles via interaction between C atom and neighbouring W atom at vacancies. This reduces the capability of helium to trap a vacancy which is required to form the bubble core and, as a consequence, delays, the bubble nucleation. At 1000 °C, significant bubble growth occurred in both materials and all the present bubbles transitioned from spherical to faceted shape, whereas at 800 °C, the faceted helium bubble population was dominated in W.
AB - Helium-induced defect nucleation and accumulation in polycrystalline W and W0.5 wt%ZrC (W0.5ZrC) were studied in-situ using the transmission electron microscopy (TEM) combined with 40 keV He+ irradiation at 800 and 1000°С at the maximum damage level of 1 dpa. Radiation-induced dislocation loops were not observed in the current study. W0.5ZrC was found to be less susceptible to irradiation damage in terms of helium bubble formation and growth, especially at lower temperature (800 °C) when vacancies were less mobile. The ZrC particles present in the W matrix pin the forming helium bubbles via interaction between C atom and neighbouring W atom at vacancies. This reduces the capability of helium to trap a vacancy which is required to form the bubble core and, as a consequence, delays, the bubble nucleation. At 1000 °C, significant bubble growth occurred in both materials and all the present bubbles transitioned from spherical to faceted shape, whereas at 800 °C, the faceted helium bubble population was dominated in W.
KW - Faceted helium bubbles
KW - In-situ helium exposure
KW - Plasma-facing materials
KW - Transmission electron microscopy
KW - Tungsten
KW - Zirconium carbide
UR - http://www.scopus.com/inward/record.url?scp=85180350035&partnerID=8YFLogxK
U2 - 10.1016/j.net.2023.12.003
DO - 10.1016/j.net.2023.12.003
M3 - Article
AN - SCOPUS:85180350035
SN - 1738-5733
VL - 56
SP - 1490
EP - 1500
JO - Nuclear Engineering and Technology
JF - Nuclear Engineering and Technology
IS - 4
ER -