Solid-State Phase Equilibria and Intermetallic Compounds of the Si-V-Zr Ternary System
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INTRODUCTION
VANADIUM alloy is the potential low-activation structural material for advanced self-cooled blanket of fusion reactors. The emphasis of the worldwide Vanadium alloy development effort has been on the V-Cr-Ti system, and a V-4Cr-4Ti alloy is regarded as the represented alloy. Recently, investigators focus their eyes on mechanical, creep, and corrosion properties under irradiation.[1–5] Significant efforts have been made in the Vanadium alloy development for Li/V blanket, because large heat of V-4Cr-4Ti ingots can be produced[6–8] For the sake of further broadening the temperature and mechanical application windows of the V-4Cr-4Ti alloy, numbers of methods have been tried, including plastic deformation and heat treatments.[9–12] Development on advanced Vanadium alloys was also carried out, such as the ultra-fine grain alloys containing Y, W, ZrO2, and TiC, which act as the strengthening phase in the alloys.[13–16] However, for the V-based alloys, several critical issues still remain unsolved or not fully understood, such as the irradiation creep and Helium embrittlement behavior. These issues should be highlighted in the future research.[17] Zr-based alloys are used as important structural materials for reactor core components due to favorable neutronic properties such as good elevated temperature mechanical properties, low-neutron absorption coefficient, and outstanding corrosion resistance in pressurized heavy water reactor condition.[18–20] For the future nuclear reactors like gas fast reactors, the cores may YANFANG PAN, HAIMEI YE, and XIAOXIAN CHEN, Ph.D. Students, WENPING JIANG and WENCHAO YANG, Lecturers, and YONGZHONG ZHAN, Professor, are with the College of Materials Science and Engineering, Guangxi University, Nanning, Guangxi 530004, P.R. China. Contact e-mail: [email protected] Manuscript submitted March 8, 2016. Article published online October 12, 2016 METALLURGICAL AND MATERIALS TRANSACTIONS A
work at high temperatures ranging from 773 K to 1273 K (500 C to 1000 C). Furthermore, current trends toward extended burn-up of the nuclear fuel in pressurized water reactors have accentuated the demand for Zr-based alloys with higher uniform corrosion resistance under irradiation and high-temperature mechanical properties.[21] To meet this requirements, an attractive solution is to combine Zr and Si into Zr silicide, that is SiXZrY, which is believed to be the potential structural materials for nuclear reactors.[22] Processing and characterization of Si2Zr3 have been studied. It is confirmed that the thermal properties [from room temperature to 1273 K (1000 C)] of Si2Zr3 satisfy the requirements related to gas fast reactors. As important structural materials for atomic energy industry, Zirconium and Vanadium have many similar properties. It is of great interest to investigate the interactions of the components in the polynary system including V, Zr, and other related elements for the development of high-performance nuclear materials. However, up to now, very few reports can be found. As part of a s
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