원자력용 개량 9Cr-1Mo 및 9Cr-0.5Mo-2W 강의 미세조직과 기계적 특성 연구

김성호; 송병준; 한창석; 국일현; 류우석; Sung Ho Kim; B.J. Song; C.S. Han; Il Hiun Kuk; Woo Seog Ryu

Korean Journal of Materials Research, Vol.9, No.11, 1137-1143, November, 1999

Export Citation

원자력용 개량 9Cr-1Mo 및 9Cr-0.5Mo-2W 강의 미세조직과 기계적 특성 연구

A Study on Microstructure and Mechanical Properties of Modified 9Cr-1Mo and 9Cr-0.5Mo-2W Steels for nuclear Power Plant

김성호, 송병준, 한창석¹, 국일현, 류우석

한국원자력연구소 원자력재료기술갤발팀
¹동경공업대학교

Sung Ho Kim, B.J. Song, C.S. Han¹, Il Hiun Kuk, and Woo Seog Ryu

Nuclear Materials Technology Development Team, KAERI, Korea
¹Tokyo Institute of Technology, Japan

초록

템퍼링 온도에 따른 기계적 특성 및 미세조직의 변화를 조사하였다. 미세조직을 관찰한 결과 템퍼링시 전위회복에 의해 형성되는 셀 구조가 나타나는 템퍼링 온도는 개량 9Cr-1Mo강의 경우 700 ? C 인 반면, 텅스텐을 첨가한 9Cr-0.5Mo-2W강의 경우는 750 ? C 이었으며, 이 결과로부터 텅스텐 첨가는 전위회복을 지연하였음을 알 수 있다. 텅스텐을 첨가하여도 템퍼링 온도에 따라 생성되는 석출물의 종류는 차이가 없었으나, 텅스텐을 첨가한 강에 있는 석출물에는 텅스텐이 포함되어 있었다. 텅스텐의 첨가로 경도값, 고온 인장강도 그리고 항복강도가 증가하였다. 이것은 텅스텐 첨가로 인한 미세구조의 안정화에 기인하는 것으로 보인다. 충격시험에서는 항복강도가 낮은 개량 9Cr-1Mo강이 더 우수한 충격파괴특성을 가졌다.

icrostructure and mechanical properties of Mod.9Cr-1Mo and W added 9Cr-0.5Mo2W steels were investigated for liquid metal reactor (LMR) heat exchange tube. The tempering temperatures at which cell structure was formed were 700 ? C for Mod.9Cr-1Mo steel and 750 ? C for W added 9Cr0.5Mo-2W steel. indicating the recovery of dislocation was delayed by the addition of W. 9Cr-0.5Mo-2W steel had the same kinds of precipitates with Mod.9Cr-1Mo steel, but the W was included in the precipitates in 9Cr-0.5Mo-2W steel. Micro-hardness and ultimate tensile strength of 9Cr-0.5Mo-2W steel were higher than those of Mod.9Cr-1Mo steel. The impact property of Mod.9Cr-1Mo steel was superior to that of 9Cr-0.5Mo-2W steel.

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[1] Fujita T, Iron and Steel Institute of Japan International, 32(2), 175 (1992)

[2] Orr J, Burton D, Ironmaking and Steelmaking, 20(5), 333 (1993)

[3] Abe F, Nakazawa S, Metall. Trans. A, 23A, 3025 (1992)

[4] Cho M, et al., Journal of the Korean Nuclear Society, 25(2), 300 (1993)

[5] Orr J, Woollard L, Strang A(ed.), Gooch DJ(ed.), The Institute of Materials, 53 (1997)

[6] Bodine GC,JR., Chakravarti B, Harkness SD, Owens CM, Roberts B, Vandergriff D, Ward CT, Pugh SF(ed.), Little EA(ed.), Pro. Inter. Conf. Ferritic Steels for Fast Reactor Steam Generator, BNES, 160 (1978)

[7] Pickering FB, Strang A(ed.), The Institute of Materials, 1 (1997)

[8] Cermak J, et al., Kov. Mater., 18, 537 (1980)

[9] Baker RG, Nutting J, Journal of the Iron and Steel Institute, 192, 257 (1959)

[10] Irvine KJ, Crowe DJ, Pickering FB, Journal of the Iron and Steel Institute, 195, 386 (1960)

[11] Little EA, Harries DR, Pickering FB, Pugh SF(ed.), Little EA(ed.), Pro. Inter. Conf. Ferritic Steels for Fast Reactor Steam Generator, 136 (1978)