Effect of titanium contents on the microstructure and mechanical properties for 9Cr2WVTa deposited metals
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Lijian Rong Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
Dianzhong Li Shenyang National Laboratory for Materials Science, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
Shanping Lua) Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China; and Shenyang National Laboratory for Materials Science, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China (Received 29 August 2016; accepted 4 January 2017)
Four 9Cr2WVTa deposited metals with different titanium contents were studied to reveal the role of minor elements titanium, which guide for the design of welding consumables for reduced activation ferritic/martensitic steel and meet for the requirements of accelerator driven systems-lead fusion reactors. The microstructural evolution of 9Cr2WVTa deposited metals was analyzed and discussed. Results show that the surface layer of 9Cr2WVTa deposited metal exhibits the columnar structure and the d-ferrite is seen as a film distributed along the martensite lath. The microstructures are uniform in the middle of the deposited metal and exhibit the equiaxed structure. The fine stripe d-ferrite decorates along the prior austenite grain boundaries and therefore, refines the grain size. The primary blocky Ti-enriched particles are the main factor affecting the mechanical properties for the 9Cr2WVTa deposited metal. The 9Cr2WVTa deposited metals obtain good mechanical properties when the titanium content does not exceed 0.08 wt%.
I. INTRODUCTION
The nuclear energy developments not only seek for the high efficiency of energy production, but also consider for the safe disposal of nuclear waste. Accelerator driven systems have been carried out widely because it has the possibility to transmute minor actinides and long lived fission products in nuclear spent fuel, that is, to realize the recycling of nuclear waste.1 The spallation target is the lead-bismuth eutectic (LBE), which requires the structural materials to have excellent irradiation resistance and good compatibility with LBE.2 Therefore, low activation elements such as tungsten, vanadium, and tantalum have been added to replace the high activation ones such as molybdenum, niobium, and nickel,3 which exhibit excellent irradiation resistance,4 good Pb–Bi corrosion resistance5 as well as good mechanical strength6 such as high temperature strength and high temperature creep property.7 Contributing Editor: Jürgen Eckert a) Address all correspondence to this author. e-mail: [email protected] DOI: 10.1557/jmr.2017.20
Reduced activation ferritic/martensitic (RAFM) steel is one of the candidate blanket structural material suited for nuclear fusion reactors because of a low coefficient of thermal expansion and excellent heat conductivity.8 The corresponding materials include the JLF-1, F82H, Eurofer97, CLAM, SIMP, and 9Cr2WVTa steel.9 The Institute of Met
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