Influence of suppressed blistering by heavy ion pre-damage on deuterium retention in tungsten

• Surface blistering creates substantial dislocations in the vicinity of blisters as revealed by EBSD and TEM results. • Fe pre-damage suppresses the formation of surface blisters, particularly for those small-sized blisters (< 6 μm). • The enhancement effect of D retention in Fe-damaged W is significantly weakened at high-fluence (3 × 10 25 D m −2 ) D exposure. • Coupled NRA and TDS analyses reveal that Fe pre-damage strongly suppresses the blistering-induced D retention in W. Surface damage and fuel retention are one of the major threats to the performance of plasma-facing materials (PFMs) in ITER and future fusion reactors. This work aims to investigate the influence of suppressed blistering by heavy ion pre-damage on deuterium (D) retention in tungsten (W). Recrystallized W samples were irradiated with 3.5 MeV iron (Fe 13+ ) ions at room temperature to create displacement damage with a peak damage level of 0.1 dpa. Afterwards, a series of low-energy (38 eV) D plasma exposures were performed at 500 K. Three exposure fluences below and above the blistering threshold (5 × 10 24 ∼ 3 × 10 25 D m −2 ) of the pre-damaged W are selected to decouple and couple the damage-induced defects and blistering-induced defects, respectively. Surface observations show that no blisters are formed in un-damaged W after low-fluence D exposure (5 × 10 24 D m −2 ), whereas severe blistering (surface coverage ratio: 34.2 %) occurs in the high-fluence case (3 × 10 25 D m −2 ). In contrast, only a small number of blisters (4.2 %) are formed in Fe-damaged W when D fluence reaches 3 × 10 25 D m −2 . Moreover, Fe pre-damage increases D retention by a factor of 3.33 and 1.20 at the low-fluence (5 × 10 24 D m −2 ) and medium-fluence (1 × 10 25 D m −2 ) D exposure, respectively. While in the high-fluence case (3 × 10 25 D m −2 ), the enhancement effect of D retention in Fe-damaged W is significantly weakened, such that retention is lower for damaged W, probably due to the significant suppression effect on surface blistering and its accompanying defect formation. This work highlights the suppressed blistering-induced D retention by pre-existing damage in W.

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Publication Details

Journal
Nuclear Materials and Energy
Published
2024-10-16
DOI
https://doi.org/10.1016/j.nme.2024.101775
Citations
2
Primary Topic
Fusion materials and technologies
Type
article
Field-Weighted Citation Impact
0.23
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article

Influence of suppressed blistering by heavy ion pre-damage on deuterium retention in tungsten

Xiu-Li Zhu, Wangguo Guo, Yue Yuan, Jipeng Zhu et al.
2 citations
Nuclear Materials and Energy
Fusion materials and technologies
0.23
article

Influence of suppressed blistering by heavy ion pre-damage on deuterium retention in tungsten

Xiu-Li Zhu, Wangguo Guo, Yue Yuan, Jipeng Zhu, Long Cheng, Shiwei Wang, Ting Wang, Guang-Hong Lü
article en
2 citations

Abstract

• Surface blistering creates substantial dislocations in the vicinity of blisters as revealed by EBSD and TEM results. • Fe pre-damage suppresses the formation of surface blisters, particularly for those small-sized blisters (< 6 μm). • The enhancement effect of D retention in Fe-damaged W is significantly weakened at high-fluence (3 × 10 25 D m −2 ) D exposure. • Coupled NRA and TDS analyses reveal that Fe pre-damage strongly suppresses the blistering-induced D retention in W. Surface damage and fuel retention are one of the major threats to the performance of plasma-facing materials (PFMs) in ITER and future fusion reactors. This work aims to investigate the influence of suppressed blistering by heavy ion pre-damage on deuterium (D) retention in tungsten (W). Recrystallized W samples were irradiated with 3.5 MeV iron (Fe 13+ ) ions at room temperature to create displacement damage with a peak damage level of 0.1 dpa. Afterwards, a series of low-energy (38 eV) D plasma exposures were performed at 500 K. Three exposure fluences below and above the blistering threshold (5 × 10 24 ∼ 3 × 10 25 D m −2 ) of the pre-damaged W are selected to decouple and couple the damage-induced defects and blistering-induced defects, respectively. Surface observations show that no blisters are formed in un-damaged W after low-fluence D exposure (5 × 10 24 D m −2 ), whereas severe blistering (surface coverage ratio: 34.2 %) occurs in the high-fluence case (3 × 10 25 D m −2 ). In contrast, only a small number of blisters (4.2 %) are formed in Fe-damaged W when D fluence reaches 3 × 10 25 D m −2 . Moreover, Fe pre-damage increases D retention by a factor of 3.33 and 1.20 at the low-fluence (5 × 10 24 D m −2 ) and medium-fluence (1 × 10 25 D m −2 ) D exposure, respectively. While in the high-fluence case (3 × 10 25 D m −2 ), the enhancement effect of D retention in Fe-damaged W is significantly weakened, such that retention is lower for damaged W, probably due to the significant suppression effect on surface blistering and its accompanying defect formation. This work highlights the suppressed blistering-induced D retention by pre-existing damage in W.

Nuclear Materials and EnergyVol. 41
North China Electric Power University (CN), Peking University (CN), Institute of High Energy Physics (CN), Science and Technology on Surface Physics and Chemistry Laboratory (CN), State Key Laboratory of Nuclear Physics and Technology, Beihang University (CN)
Openalex Percentile: Top 51%
Fusion materials and technologies
0.23
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