摘要
Tungsten-potassium(WK)alloy with ultrafine/fine grains and nano-K bubbles is fabricated through spark plasma sintering(SPS)and rolling process.In this study,3-MeV W^2+ ion irradiation with a tandem accelerator is adopted to simulate the displacement damage caused by neutrons.As the depth of irradiation damage layer is limited to only 500 nm,the hardening behaviors of WK alloy and ITER(International Thermonuclear Experimental Reactor)-W under several damage levels are investigated through Bercovich tip nanoindentation test and other morphological characterizations.The indenter size effect(ISE),soft substrate effect(SSE),and damage gradient effect(DGE)are found to influence the measurement of nano-hardness.Few or no pop-ins in irradiated samples are observed while visible pop-in events take place in unirradiated metals.Extensive pile-up with different morphology features around the indentation exists in both WK and ITER-W.The WK shows a smaller hardness increment than ITER-W under the same condition of displacement damage.This study provides beneficial information for WK alloy serving as a promising plasma facing materials(PFMs)candidate.
作者
杨晓亮
陈龙庆
邱文彬
宋阳一鹏
唐毅
崔旭东
刘长松
蒋燕
张涛
唐军
Xiao-Liang Yang;Long-Qing Chen;Wen-Bin Qiu;Yang-Yi-Peng Song;Yi Tang;Xu-Dong Cui;Chang-Song Liu;Yan Jiang;Tao Zhang;Jun Tang(Key Laboratory of Radiation Physics and Technology of Ministry of Education,Institute of Nuclear Science and Technology,Sichuan University,Chengdu 610064,China;Sichuan Research Center of New Materials,Institute of Chemical Materials,China Academy of Engineering Physics,Mianyang 621999,China;Key Laboratory of Materials Physics,Institute of Solid State Physics,Chinese Academy of Sciences,Hefei 230031,China)
基金
Project supported by the National Natural Science Foundation of China(Grant Nos.11975160,11775149,and 11475118)
the International Thermonuclear Experimental Reactor(ITER)Program Special,China(Grant No.2011GB108005)。