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

Asril Pramutadi Andi Mustari*, Minoru Takahashi

*この研究の対応する著者

    研究成果: Article査読

    9 被引用数 (Scopus)

    抄録

    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.

    本文言語English
    ページ(範囲)1073-1077
    ページ数5
    ジャーナルProgress in Nuclear Energy
    53
    7
    DOI
    出版ステータスPublished - 2011 9

    ASJC Scopus subject areas

    • エネルギー工学および電力技術
    • 原子力エネルギーおよび原子力工学
    • 廃棄物管理と処理
    • 安全性、リスク、信頼性、品質管理

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