Correlation between the microstructure, mechanical/thermal properties, and thermal shock resistance of K-doped tungsten alloys

Huang, Bo; Chen, Lei; Qiu, Wenbin; Yang, Xiaoliang; Shi, Ke; Lian, Youyun; Liu, Xiang; Tang, Jun

doi:10.1016/j.jnucmat.2019.03.056

Cited by 34 publications

(19 citation statements)

References 44 publications

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“…The UTS of KB-W is ~ 150 MPa higher than that of PW at temperatures from RT to 873 K. There is at least 50% of increment in the K IC through the three-point bending tests at temperatures from RT to 1473 K. Roughly speaking, strength and toughness in metals are inevitably a trade-off, but in KB-W, not only the hardness and UTS are improved, but also K IC is enhanced clearly [52]. Huang et al [73] and Tang et al [74] further rolled and forged the SPS-WK bulks and found that the best K content was ~ 82 ppm and the recrystallization temperature (Rct) was still larger than 2073 K.…”

Section: Mechanical Properties Of Wkmentioning

confidence: 99%

“…Systematical studies on the ductile-brittle transition of nano-K-bubble-strengthened WK (KB-W) were carried out [25,52,65,66,73,74]. Table 1 and Fig.…”

Section: Mechanical Properties Of Wkmentioning

confidence: 99%

“…The cracking threshold was an intuitive parameter of the thermal resistance for PFMs. To find the cracking threshold of WK, Huang et al [52,73] conducted a 5-ms electron pulse on the KB-W samples with different power densities at RT in Southwestern Institute of Physics to simulate the plasma disruption in Tokamaks. The three-dimensional (3D) surface morphologies and SEM images in Fig.…”

Section: Resistance To Thermal Loadsmentioning

confidence: 99%

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Tungsten–potassium: a promising plasma-facing material

2019

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Tungsten-potassium (potassium-doped tungsten or WK), initially known from the electric filament industry, is a promising plasma-facing material (PFM) in future fusion facilities like International Thermonuclear Experimental Reactor (ITER). However, the brittle nature of W and irradiation-induced defects of WK materials may result in a risk of deuterium-tritium reaction failure in fusion reactors. Previous studies revealed that advanced W with ultrafine grains and nanostructures might be able to address these problems. However, K-doped W, a rapidly developed material for PFMs, lacks a systematical summary. In this review, we firstly describe the powder metallurgy and plastic deformation for the preparation of WK. Then, the mechanical properties of WK and thermal shock resistance results are reviewed. Important issues such as irradiation damages from neutron, heavy ion, and plasma (H isotope or He) irradiation are also discussed. Hitherto, WK under irradiations shows comparable or even better performances compared with other counterparts such as ITER grade pure tungsten. This review could be benefitial to the future efforts of improving the ductility and irradiation tolerance of WK materials.

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Section: Mechanical Properties Of Wkmentioning

confidence: 99%

“…Systematical studies on the ductile-brittle transition of nano-K-bubble-strengthened WK (KB-W) were carried out [25,52,65,66,73,74]. Table 1 and Fig.…”

Section: Mechanical Properties Of Wkmentioning

confidence: 99%

Section: Resistance To Thermal Loadsmentioning

confidence: 99%

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Tungsten–potassium: a promising plasma-facing material

2019

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“…Chen et al [11] confirmed that the grain boundaries played a decisive role in defects annihilation using the in-situ observation and simulation, which delayed the surface blistering of nanocrystalline W significantly compared with the coarse-grained W. Moreover, the interfaces have been proved that it can effectively attract, absorb and annihilate irradiation-induced defects. Due to the large amount of interfaces between the matrix and nanoscale dispersion, the dispersion-strengthen W based alloys such as W-V [12], W-K [13], W-La 2 O 3 [14], and W-TiC [15] have higher radiation tolerance than that of the pure W. The multilayer nanofilms (such as Cu/W [16], ZrO 2 /W [17], and Cr/W [18]) deposited by magnetron sputtering showed an excellent radiation tolerance owing to the introduction of interfaces. Encouragingly, the researchers have demonstrated this idea using the bulk nanocomposites through accumulative roll bonding (ARB) [19,20].…”

Section: Introductionmentioning

confidence: 99%

Review on helium behaviors in nanochannel tungsten film

et al. 2021

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Tungsten (W) as plasma facing material (PFM) needs to face an unprecedented harsh environment in the fusion reactor, which puts forward high requirements for its radiation tolerance. Among the many challenges, the rapid accumulation of helium (He) atoms to form numerous bubbles or even "fuzzy" nanostructure leads to swelling and embrittlement of W matrix and seriously shorten its service life, which is one of the most serious problems faced by PFM-W at present. In this review, we summarize the recent works on the nanochannel W films with high surface-to-volume ratio deposited by magnetron sputtering, and the behaviors of He in the nanochannel W films at different fusion-related irradiation environment. Experimental and simulation results showed that the nanochannel W films have better radiation tolerance performance in managing He behaviors than that of commercial bulk W.

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“…[ 12–14 ] A WK alloy with 82 ppm K has thus far exhibited the best tensile strength and thermal shock resistance among K‐doped W materials with different K content. [ 15 ] Therefore, because of their excellent mechanical properties, the irradiation tolerance of WK alloys has gradually gained widespread attention. Spark‐plasma‐sintered (SPS) WK alloys exhibit a smooth surface morphology after He plasma irradiation because K bubbles hinder the movement of defects.…”

Section: Introductionmentioning

confidence: 99%

Vacancy‐Type Defects in H+6%He Neutral Beam Irradiated WK Alloy Probed by Slow Positron Beam

Liu

Pei-Yuan

et al. 2021

Physica Status Solidi (a)

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H+6%He mixed neutral beam with a power density of 8 MV m−2 and fluence of 1025 m−2 is produced to induce irradiation damage at surface temperatures of 400, 800, and 1300 °C in WK alloy, and at 400 and 800 °C in pure W samples. Doppler‐broadening positron annihilation spectroscopy (DB‐PAS) and X‐ray diffraction (XRD) are used to probe the evolution of vacancy‐type defects in the samples after irradiation. The results show that for the WK alloy, the S‐parameters for the 400, 800, and 1300 °C samples increase sequentially because of the increase in vacancy‐type defect concentrations or volumes. The WK sample at 1300 °C exhibits a wider defect damage layer and more complicated vacancy‐type defects than those in the WK samples at 400 and 800 °C. For pure W, the S‐parameter of the 800 °C samples is larger than that of the 400 °C samples, which is attributed to the aggregation and growth of vacancy‐type defects. Based on a comparison of the WK and pure W samples, the pinning effect of K bubbles in the WK samples has an influence on the transportation of H/He atoms and the migration and aggregation of vacancy‐type defects.

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Correlation between the microstructure, mechanical/thermal properties, and thermal shock resistance of K-doped tungsten alloys

Cited by 34 publications

References 44 publications

Tungsten–potassium: a promising plasma-facing material

Tungsten–potassium: a promising plasma-facing material

Review on helium behaviors in nanochannel tungsten film

Vacancy‐Type Defects in H+6%He Neutral Beam Irradiated WK Alloy Probed by Slow Positron Beam

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