Surface modification and deuterium retention in hot-rolled potassium doped tungsten alloy exposed to deuterium plasma

Ma, Xiaolei; Wang, Ting; Zhang, Xiaoxin; Yuan, Yue; Cheng, Long; Zhu, Jinhua; Lv, Wei; Lang, Shaoting; Wang, Zihao; Chen, Ge; Yan, Qingzhi

doi:10.1016/j.jnucmat.2022.153890

Cited by 4 publications

(3 citation statements)

References 54 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 addition, K bubbles also play an important role in the formation and evolution of D blisters. A detailed analysis and discussion can be found in our previous work [61]. Therefore, we only focus on the effect of pre-damage on the surface morphology evolution of PW and KW after D plasma exposure in this section.…”

Section: Effect Of Fe 11+ Pre-damage On Surface Morphology Evolution ...mentioning

confidence: 99%

“…Figure 8 presents the total D retention in undamaged and pre-damaged PW and KW. Obviously, the KW-0 dpa sample can induce more D retention than PW-0 dpa, and our previous work contains a detailed analysis and discussion of this phenomenon [61]. Hence, we only focus on the effect of predamage on the total D retention of PW and KW in this section.…”

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

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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Effect of Fe11+ ion combined with helium and deuterium plasmas irradiation on the transient thermal shock behaviors of pure and potassium-doped tungsten

Feng

Zhang

et al. 2023

Journal of Nuclear Materials

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Surface modification and deuterium retention in hot-rolled potassium doped tungsten alloy exposed to deuterium plasma

Cited by 4 publications

References 54 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

Effect of Fe11+ ion combined with helium and deuterium plasmas irradiation on the transient thermal shock behaviors of pure and potassium-doped tungsten

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