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임혁순(Hyuk-Soon LIM),박영섭(Young-Sheop PARK),이광한(Kwang-Han LEE),이석호(Seok-Ho LEE),정대율(Dae-Yul CHUNG) 대한기계학회 2004 대한기계학회 춘추학술대회 Vol.2004 No.4
Inconel-600 alloy has been used as steam generator tube material for current pressurized water reactors (PWRs). The long-term operation of steam generators showed that the use of this material induced localized corrosion damages and increased tube wear of steam generator. To protect these problems, steam generator tube material is being changed to Inconel-690 alloy. Based on the current trend, we have chosen Inconel 690 as the Advanced Power Reactor 1400 (APR1400) steam generator(SG) tube material and performed the design optimization of preventive measure against tube fretting wear for the APR1400 steam generator. In this paper, we examined the technical consideration in this modification : the selection of material, wear characteristics, effect of the Egg-crate Flow Distribution Plate installation, and effect analysis of vertical strip installation.
신형경수로의 증기발생기 전열관 재질 Inconel-690 적용
임혁순(Hyuk-Soon LIM),정대율(Dae-Yul CHUNG),변성철(Sung-chul BYUN),이광한(Kwang-Han LEE) 대한기계학회 2003 대한기계학회 춘추학술대회 Vol.2003 No.4
Most of the operating pressurized water reactors (PWRs) has chosen Inconel 600 as steam generator tubing. The long-term operation of steam generators showed that the use of this material induced localized corrosion damages. The current trend is using Inconel 690 as a tube material for the replacement steam generators. Based on the current trend, we have chosen Inconel 690 for the Advanced Power Reactor 1400 (APR1400) steam generator tube material. In this paper, we examined the technical consideration in this modification:the effect of chemical composition, thermal conductivity, corrosion resistance and wear characteristics