Effect of pre-damage induced by argon ions on the deuterium blister formation in tungsten-tantalum alloys exposed to deuterium plasma

Zhou, Hang; Yu, Jiangang; Chen, Changan; Zhu, Kaigui

doi:10.1016/j.ijhydene.2019.07.061

Cited by 18 publications

(9 citation statements)

References 51 publications

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“…Therefore, the high-energy heavy ion predamage can reduce the D retention in W under certain conditions. In order to make this mechanism easier for the reader to understand, we have made some reasonable inferences by combining previous reports [38,41,51,74,86] and the results of this work. It is speculated that there are three D fluence regions; namely, less than ∼10 25 m −2 (region A), ∼10 25 -10 26 (region B), and over 10 26 (region C).…”

Section: The Tds Of D In Undamaged and Pre-damaged Pw And Kwmentioning

confidence: 91%

“…In fact, conclusion (a) is a fascinating result, and this phenomenon has hardly been mentioned in previous reports. A large number of research results show that heavy ion damage can increase D retention in W [38,41,51,74,86]. The reason for the two opposite conclusions may be due to the different D fluences during plasma exposure.…”

Section: The Tds Of D In Undamaged and Pre-damaged Pw And Kwmentioning

confidence: 99%

“…However, the disadvantages of the exceedingly high experimental cost, considerable experimental cycle and lack of neutron sources seriously limit the wide application of the neutron irradiation experiment. Indeed, high-energy heavy ion irradiation can be used to simulate neutron irradiation, because heavy ion irradiation can produce vacancy clusters in the same way as neutron irradiation [38]. Consequently, heavy ion irradiation has become one of the best choices for simulating neutron irradiation due to its short experimental cycle, low experimental cost and abundant ion source [39].…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Decreased surface blistering and deuterium retention in potassium-doped tungsten exposed to deuterium plasma following ion irradiation

Zhang

Wang

et al. 2023

Nucl. Fusion

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A large-size potassium-doped tungsten (KW) plate with a thickness of 15 mm was fabricated via powder metallurgy technology and hot rolling. In order to appraise the irradiation resistance of KW, the surface deuterium (D) blistering and D retention were studied on Fe11+ pre-damaged (0, 0.05 & 0.5 dpa) KW and pure tungsten (PW), which were exposed to ~60 eV and ~ 5 × 1021 m-2 s-1 D plasmas at 500 K to a fluence of ~ 5.76 × 1025 m-2. The results indicated that the KW alloy can inhibit the generation of vacancy defects after Fe11+ ion damage compared with PW because K bubbles can restrain the migration of W self-interstitial atoms and the accumulation of vacancies caused during Fe11+ ion irradiation. The Fe11+ ions pre-damage can relieve the surface blistering and D retention of PW and KW at the same time and the KW has a better effect on inhibiting D retention, while does not shows a significant advantage for inhibiting surface blistering compared with PW. Besides, the causes for the discrepancy in total D retention and surface morphology evolution of PW and KW were discussed in detail.

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Section: The Tds Of D In Undamaged and Pre-damaged Pw And Kwmentioning

confidence: 91%

Section: The Tds Of D In Undamaged and Pre-damaged Pw And Kwmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Decreased surface blistering and deuterium retention in potassium-doped tungsten exposed to deuterium plasma following ion irradiation

Zhang

Wang

et al. 2023

Nucl. Fusion

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“…It has been reported that the K-doped tungsten fabricated with sparking plasma sintering (SPS) shows good thermal conductivity, as well as strong mechanical properties at temperatures from RT to 50 • C [6]. Alloying elements like tantalum (Ta), vanadium (V), chromium (Cr) and rhenium (Re) are also being intensively studied [10][11][12][13][14][15]. It has been reported that tantalum alloying contributes to improving the hardness and bending strength of W [14], and can be expected to suppress surface blistering and reduce the deuterium retention in tungsten [15].…”

Section: Introductionmentioning

confidence: 99%

Properties of Potassium Doped and Tantalum Containing Tungsten after Heavy Ion Irradiation

Zhao

et al. 2023

Crystals

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Tungsten potassium (WK) alloy has been reported as one of the ideal plasma-facing materials (PFMs). Tantalum alloying is a good method to improve the mechanical properties of tungsten. The effect of tantalum contents on the irradiation resistance of WK alloy has not yet been reported. In this study, WK (containing 82 ppm potassium) alloy with 1 wt. % Ta and 3 wt. % Ta, specifically WK-1Ta and WK-3Ta, were fabricated with sparking plasma sintering and irradiated with 7.5 MeV W2+ ion. The relative densities of WK-1Ta and WK-3Ta are 97.2% and 96.4%, respectively. The average grain sizes of WK-1Ta and WK-3Ta are 2.08 μm and 1.51 μm, respectively. The Vickers hardness of WK-3Ta is nearly 20% higher than that of WK-1Ta, both before and after irradiation. Irradiation hardening was confirmed by nano indentation test results. After irradiation, the number of dislocation loops formed in WK-1Ta and WK-3Ta are very similar, and the dislocation loop density of WK-3Ta is only slightly higher than that of WK-1Ta. This phenomenon is consistent with nano hardness analysis results. Compared to the reported nano hardness results of WK alloys, both WK-1Ta and WK-3Ta had higher hardness than the WK alloys before irradiation. Compared to the irradiation hardening results for the reported WK alloys, the existence of Ta may have positive influence on resistance to irradiation hardening.

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“…As the PFMs, W will inevitably be irradiated by high-density hydrogen isotope plasma and undergo serious surface modification. Previous research has shown that surface blistering [6][7][8][9][10][11][12], melting [13] and cracking [13] occurred on the W under deuterium (D) irradiation. These are detrimental to the properties of W. In order to study the underlying physical mechanism of surface blistering and hydrogen retention in W, a series of experiments were carried out.…”

Section: Introductionmentioning

confidence: 99%

Effect of anisotropic grain boundaries on the surface blistering of tungsten induced by deuterium plasma exposure

Xia¹,

Jiang²,

Shi³

et al. 2022

Phys. Scr.

Self Cite

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The effect of anisotropic grain boundaries on the surface microstructure changes and deuterium retention behavior in tungsten under deuterium plasma irradiation were studied. The samples named as NDW and RDW were cut from RD × TD plane and TD × ND plane of a rolled W plate (ND: normal direction, RD: rolling direction, TD: transverse direction), respectively. The results suggest that both surface morphology and deuterium retention in the RDW samples are suppressed compared to that of NDW samples for 1 h and 25 h deuterium irradiation. For 1 h exposure, the total deuterium retention in the NDW samples is about 1.6 times as much as that of RDW. However, as the exposure time increased to 25 h, the total deuterium retention in the NDW sample is two times the height of RDW sample. The experimental results show that the special grain structure of RDW can alleviate the surface morphology changes and decrease the deuterium retention in tungsten, which is interpreted by the lateral stress model of blistering.

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Effect of pre-damage induced by argon ions on the deuterium blister formation in tungsten-tantalum alloys exposed to deuterium plasma

Cited by 18 publications

References 51 publications

Decreased surface blistering and deuterium retention in potassium-doped tungsten exposed to deuterium plasma following ion irradiation

Decreased surface blistering and deuterium retention in potassium-doped tungsten exposed to deuterium plasma following ion irradiation

Properties of Potassium Doped and Tantalum Containing Tungsten after Heavy Ion Irradiation

Effect of anisotropic grain boundaries on the surface blistering of tungsten induced by deuterium plasma exposure

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