Irradiation hardening behaviors of large-scale hot rolling potassium-doped tungsten alloy under synergistic irradiations of Fe11+ ion combined with deuterium and helium plasmas

Ma, Xiaolei; Zhang, Xiaoxin; Wang, Ting; Lv, Wei; Lang, Shaoting; Chen, Ge; Yan, Qingzhi

doi:10.1016/j.nme.2022.101138

Cited by 4 publications

(4 citation statements)

References 59 publications

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“…the thickness of the W-Cu mono-block as a divertor component is not less than 12 mm [33]. Furthermore, some of its key properties have been characterized and the results indicate that the W-K exhibits high strength and large plasticity simultaneously, superior high-temperature stability [34], good plasma exposure resistance [35] and excellent irradiation hardening resistance [36]. In order to more systematically evaluate the service performance of this W-K plate, it is very important and necessary to investigate its thermal shock resistance.…”

Section: Introductionmentioning

confidence: 99%

Effect of potassium bubbles on the thermal shock fatigue behavior of large-volume potassium-doped tungsten alloy

Feng

Zhang

et al. 2022

Nucl. Fusion

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A newly developed large-volume potassium doped tungsten (W-K) plate with a thickness of 15 mm and a weight of 25 kg by powder metallurgy plus hot rolling was prepared to meet the requirements of International Thermonuclear Experimental Reactor (ITER) in engineering application. In order to clarify the effect of K doping on the thermal shock performance of W-K alloy, transient thermal shock tests with a single pulse duration of 1 ms for 100 shots at room temperature were performed. The absorbed power density is set to 0.33, 0.44, 0.55 and 0.66 GW/m2, respectively. Besides, the microstructure, Vickers micro-hardness before and after the transient thermal shock, thermal conductivity and relative density were also characterized. The results indicate that the cracking threshold of rolled W-K is 0.44-0.55 GW/m2, which possesses a better transient thermal shock resistance compared with the most of advanced W-based materials. This is mainly because that K doping can significantly improve the high-temperature stability and mechanical properties of W material without reducing its thermal conductivity. Especially, K bubbles can also effectively inhibit the formation and propagation of crack during thermal shock. Moreover, the cracking mechanism of rolled W-K alloy was also discussed in details. These studies are helpful to build a trusted ITER database on an advanced W-based materials, which provides useful references for the selection of future plasma facing materials.

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Section: Introductionmentioning

confidence: 99%

Effect of potassium bubbles on the thermal shock fatigue behavior of large-volume potassium-doped tungsten alloy

Feng

Zhang

et al. 2022

Nucl. Fusion

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“…In summary, under the combined action of Fe ion damage and D plasma exposure, KW is able to more effectively inhibit surface blistering and reduce D retention compared with PW. When combined with our previous research results on KW [19,27,29,30], which has excellent mechanical properties, superior high-temperature stability, good radiation hardening resistance and outstanding thermal shock resistance, it can be concluded that KW alloys are a very promising candidate for PFMs. These studies play an important role in the development of PFMs for future fusion reactors.…”

Section: Discussionmentioning

confidence: 52%

“…ensuring the thickness of the W-Cu mono-block as the divertor component is not less than 12 mm [28], a large-scale KW plate with a thickness of 15 mm was prepared via powder metallurgy and hot rolling; a DBTT of 373 K was measured through tensile testing, and the recrystallization temperature was higher than 2073 K [29]. Moreover, the 15 mm KW plate also has good irradiation hardening resistance and mechanical behavior [29,30]. In view of the above description, it should be emphasized here that for the same sample, the DBTT obtained is very different when using different testing methods, such as Charpy impact, tensile and bending tests, , and was also clearly verified by the studies of Nogami et al [31][32][33][34].…”

Section: Introductionmentioning

confidence: 99%

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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“…Potassium doping has already proved its efficiency in suppressing secondary recrystallization and controlling grain growth up to 1900 • C in tungsten thin wires, and therefore shows extraordinary properties at elevated temperatures [4]. Potassium-doped (K-doped) tungsten bulk material becomes an attractive candidate for the plasma-facing material as well [5][6][7][8][9]. 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].…”

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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Irradiation hardening behaviors of large-scale hot rolling potassium-doped tungsten alloy under synergistic irradiations of Fe11+ ion combined with deuterium and helium plasmas

Cited by 4 publications

References 59 publications

Effect of potassium bubbles on the thermal shock fatigue behavior of large-volume potassium-doped tungsten alloy

Effect of potassium bubbles on the thermal shock fatigue behavior of large-volume potassium-doped tungsten alloy

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

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