Study on corrosion of welded steel for LBE-cooled fast reactors

Asril Pramutadi Andi Mustari*, Minoru Takahashi

*Corresponding author for this work

    Research output: Contribution to journalArticlepeer-review

    14 Citations (Scopus)


    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.

    Original languageEnglish
    Pages (from-to)1073-1077
    Number of pages5
    JournalProgress in Nuclear Energy
    Issue number7
    Publication statusPublished - 2011 Sept


    • Corrosion
    • Ferritic-martensitic steel
    • Lead-bismuth eutectic
    • Welding

    ASJC Scopus subject areas

    • Energy Engineering and Power Technology
    • Nuclear Energy and Engineering
    • Waste Management and Disposal
    • Safety, Risk, Reliability and Quality


    Dive into the research topics of 'Study on corrosion of welded steel for LBE-cooled fast reactors'. Together they form a unique fingerprint.

    Cite this