Mechanical properties and thermal shock resistance of tungsten alloys strengthened by laser fragmentation-processed zirc
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Tungsten https://doi.org/10.1007/s42864-020-00071-5
www.springer.com/42864
ORIGINAL PAPER
Mechanical properties and thermal shock resistance of tungsten alloys strengthened by laser fragmentation‑processed zirconium carbide nanoparticles Ke Jing1,2 · Chao Zhang1,2 · Rui Liu1 · Zhuo‑Ming Xie1 · Lin‑Chao Zhang1 · Li‑Feng Zhang1,2 · Jun Liu1 · Rui Gao1 · Jun‑Feng Yang1 · Xian‑Ping Wang1 · Ting Hao1 · Xue‑Bang Wu1 · Qian‑Feng Fang1,2 · Chang‑Hao Liang1 · Guang‑Nan Luo3 · You‑Yun Lian4 · Xiang Liu4 · Chang‑Song Liu1 Received: 19 August 2020 / Revised: 18 September 2020 / Accepted: 19 September 2020 © The Nonferrous Metals Society of China 2020
Abstract Zirconium carbide (ZrC) nanoparticles with an average size of 5.6 nm were synthesized through laser fragmentation (LF) from as-received 20–60 nm ZrC particles, and LF-ZrC nanoparticle dispersion-strengthened tungsten (LF-WZC) samples were fabricated by spark plasma sintering method. The average grain size of LF-WZC is 1.91 μm and most ZrC particles in LF-WZC are smaller than 10 nm. LF-WZC exhibits finer grain size, higher yield strength and hardness but lower ductility as compared with W-ZrC samples using as-received ZrC (WZC). The results showed that finer ZrC nanoparticles dispersed in tungsten can enhance the strength by hindering the motion of dislocations, but they may also introduce stress concentration and thus reduce the ductility. The thermal shock resistance of the WZC and LF-WZC samples was investigated using an electron beam device. The LF-WZC sample also exhibits a higher cracking threshold (0.33–0.44 GW·m−2) than WZC (0.22–0.33 GW·m−2) at room temperature. The enhanced thermal shock resistance of LF-WZC could be attributed to its high yield strength. Keywords Tungsten · Mechanical properties · ZrC · Laser fragmentation · Thermal shock resistance
1 Introduction Tungsten, as a refractory metal, has a series of excellent properties such as high melting temperature (3410 °C), high thermal conductivity, low tritium retention and low sputtering yield, and is regarded as the most promising candidate Ke Jing and Chao Zhang contributed equally to this work. * Rui Liu [email protected] * Xian‑Ping Wang [email protected] 1
Key Laboratory of Materials Physics, Institute of Solid State Physics, HFIPS, Chinese Academy of Sciences, Hefei 230031, China
2
University of Science and Technology of China, Hefei 230026, China
3
Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China
4
Southwestern Institute of Physics, Chengdu 610041, China
materials for plasma–facing materials (PFMs) in future fusion reactors [1–3]. However, the serious embrittlement of tungsten, i.e., recrystallization embrittlement, low-temperature embrittlement and radiation-induced embrittlement, severely limited its practical application [4–6]. In future fusion devices, high service temperatures [7] can degrade the strength of tungsten materials and lead to severe embrittlement by recrystallization and grain growth [8, 9]. Besides, the transient thermal loads wit
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