A Study on the Mechanical Strength Change by Thermal Aging of 2.25Cr-1Mo Steel

발전설비용 2.25Cr-1Mo 강의 시효에 의한 기계적 강도 특성 변화에 대한 연구

  • Published : 2000.07.01


The purpose of this study is to investigate the thermal embrittlement and the mechanical properties of 2.25Cr-1Mo steel aged at high temperature for the extended periods. Original, aged artificiall y and used material were tested to obtain the tensile strength, hardness and impact absorbed energy. Tensile strength, hardness and impact absorbed energy decreased with the increasing aging time. The carbide morphology with the thermal embrittlement was found to contribute to the mechanical property change by X-Ray diffraction method.


Thermal Embrittlement;Carbide Extract;Fatigue Test;Energy Transition Temperature;High Temperature Tensile Test


  1. Arrouz, A., Collins, M.J., and Pilkington, R., 1983, 'Microstructural examination of 1Cr-0.5Mo steel during creep,' Metals Technology, Vol. 10, pp. 461-463
  2. Kleuh, R.L. and Maziasz, P.J., 1989, 'The Microstructure of Chromium-Tungsten Steel,' Met. Trans., Vol. 20A, pp. 373-382
  3. Seung-Gun Lee, Yoon-Suk Chang and Tae-Eun Jin, 1999, 'Material Property Determination of Aged Cast Autenitic Stainless Steel Componens for LBB Application,' Tran. Of 15th Int. Conference on Struc. Mech. In Reactor Tech., pp. III-167-III-174
  4. 金正基, 尹在永, 宋基旭, 李株鎭, 鄭世喜, 1991, '입계부식법에 의한 플랜트용 고온용기의 경년재질열화 평가에 관한 연구,' 대한기계학회논문집, 제15권, 제3호, pp. 898-906
  5. Iwadate, T., Watanabe, J., and Tanaka, Y., 1985, 'Prediction of the Remaining Life of High Temperature/Pressure Reactor Made of Cr-Mo Steels,' Trans. of the ASME Jour. of Pressure Vessel Technology, Vol. 107, pp. 230-238
  6. Iwadate, T., Karaushi, T. and Watanabe, J., 1977, 'Prediction of Fracture Toughnessrm KIC of 2 1/4 Cr-1 Mo Pressure Steels from Charpy V-Notched Test Results,' ASTM STP 631, pp. 493-506
  7. Roberts, Richard, Krishna, G.V., and Nishanian, Jerar, 1980, 'Fracture Behavior of A36 Bridge Steels,' ASTM STP 700, pp. 552-577
  8. Stahlkopf, K.E., Smith, R.E., Server, W.L. and Wullaert, R.A., 1975, 'Preliminary Results of a Program for Developing Fracture Toughness Data on Ferric Nuclear Pressure Vessel Steel,' ASTM STP 601, pp. 291-307
  9. Challenger, K. D. and Miller, A. K., 1981, 'An Explanation for the Hold Period on the Elevated Temperature Fatigue Behavior of 2 1/4 Cr-1 Mo Steel,' Tran. of the ASME Jour. of Eng. Mat. and Tech., Vol. 103, pp. 7-14
  10. 許聖康, 洪炅兌, 都正萬, 1994, '고온설비의 잔존수명 예측법,' 대한금속학회회보, 제7권, 제4호, pp. 356-371
  11. Yutaka Watanabe and Tetsuo Shoji, 1991, 'The Evaluation of In-service Materials Degradation of Low-alloy Steel by the Electrochemical Method,' Metal. Trans., A, Vol. 22A, Sep, pp. 2097-2106
  12. Nishizaka, Y., Hara, Y., Hori, A., Ysukahara, H., Miyano, K., Wada, T. and Cox, T.B., 1985, 'Changes in Microstructure and Mechanical Properties of Cr-Mo Reactor Vessel Steels during long-time service,' Trans. of ASME, Jour. of Pressure Vessel Technology, Vol.107, Aug. pp. 285-294