Study on corrosion of welded steel for LBE-cooled fast reactors |
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Authors: | Asril Pramutadi Andi Mustari Minoru Takahashi |
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Affiliation: | a Department of Nuclear Engineering, Graduate school of Engineering and Science, Tokyo Institute of Technology, N1-18, 2-12-1, Ookayama, Meguro-ku, Tokyo 152-8550, Japan b Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, N1-18, 2-12-1, Ookayama, Meguro-ku, Tokyo 152-8550, Japan |
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Abstract: | Lead-bismuth eutectic (LBE) is a candidate coolant for fast reactors. Its physical, chemical and neutronic properties make it a prospect coolant for the reactors. However, corrosion of structure is the main problem of utilizing LBE as a coolant. Compatibility of welded structure with LBE at high temperature should be considered clearly for feasibility of lead-bismuth-cooled fast reactors. This study was preformed to investigate the mechanical properties and corrosion characteristics of the welded ferritic-martensitic (FM) steel, HCM12A, in LBE at 650 °C for 500 h. The welding methods were TIG welding (137 mm/min; 480 W), YAG laser welding (780 mm/min; 287 W) and electron beam welding (1000 mm/min; 60 kW). The oxygen concentration of test environment was maintained at 7 x 10−7 wt% by injecting Ar-H2-steam gas mixture. Vickers hardness test and SEM/EDX analysis were conducted on the cross section of welded HCM12A. It was found that oxide layer was larger in the weld zones than base metal (BM). However, outer layer was detached on some areas. |
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Keywords: | Lead-bismuth eutectic Corrosion Welding Ferritic-martensitic steel |
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