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Okubo, Nariaki; Kondo, Keietsu; Kitamura, Akane; Okuno, Yasuki
no journal, ,
Research and development of ADS and TEF-T have been done by JAEA. ADS and TEF-T adopt liquid lead bismuth eutectic (LBE) for both spallation target and coolant for the non-critical core. Irradiation and corrosion behaviors of steel materials in LBE are one of the important issues. High energy proton beam and spallation neutron irradiation will cause high dose of displacement damage and high concentration of transmutation gas, helium and hydrogen, simultaneously, in the target window material. At once, the materials will be influenced by the corrosion and erosion, which depends on the irradiation temperature and oxygen concentration in LBE, under LBE flow. Then, the irradiation data for material properties of corrosion/erosion and mechanical changes in flowing LBE is necessary to design and evaluate lifetime of ADS components. It is possible that the TEF-T facility will achieve the irradiation, which covers the ADS conditions of temperature from 450 to 550 and the displacement damage up to 20 dpa as designed for ADS target window. Material issues for the target window, irradiation plan of TEF-T, and the present activities for material test proceeded in static LBE pot and LBE loop systems will be presented.
Okubo, Nariaki; Fujimura, Yuki; Kitamura, Akane; Okuno, Yasuki
no journal, ,
Japan atomic energy agency has been conducting research activities for developing the accelerator driven system (ADS), which is expected to reduce and transmute radioactive wastes involved in spent fuels by nuclear power plants. The ADS adopts a liquid metal of lead-bismuth eutectic (LBE) as a coolant and also spallation target to produce high energy neutrons. In this study, effect of irradiation on corrosion behavior was evaluated for 316L stainless steel and T91 ferritic martensitic steel, which are candidate materials of ADS target window, through the immersion test under LBE with saturated and low oxygen concentration followed by ion irradiation experiment. In the case of soaking in LBE with saturated oxygen concentration for SS316L steels at 450
C, 330 hrs, non-irradiated region did not show clear oxide layer, however, irradiated region showed bi-layers of magnetite and spinel type oxides. The formation rate of oxide layer for irradiated region, 26 
m/year, was about twice faster than that of non-irradiated region, 12 m/year. This result suggests that diffusion behavior after irradiation and mass transfer in the interface between LBE and steel surface is important for understanding of irradiation effect on liquid metal corrosion.
Okubo, Nariaki; Fujimura, Yuki
no journal, ,
The accelerator driven system (ADS) adopts a liquid metal of lead-bismuth eutectic (LBE) as a coolant and also spallation target to produce high energy neutrons. In this study, irradiation effect on the corrosion behavior was evaluated for the compativility of 316L stainless steel, which is candidate material of ADS target window, through the immersion test under LBE with saturated and low oxygen concentration followed by ion irradiation experiment. In the case of soaking in LBE with saturated oxygen concentration for SS316L steels at 450C, 330 hrs, non-irradiated region did not show clear oxide layer, however, irradiated region showed bi-layers of magnetite and spinel type oxides. The formation rate of oxide layer for irradiated region was about twice faster than that of non-irradiated region. This result suggests that diffusion behavior after irradiation and mass transfer in the interface between LBE and steel surface is important for understanding of irradiation effect on liquid metal corrosion.