Creep–Fatigue Damage Evaluation of 2.25Cr-1Mo Steel in Process Reactor Using ASME-NH Code Methodology

  • Sagar R. DukareEmail author
  • Nilesh R. Raykar
Conference paper
Part of the Lecture Notes in Mechanical Engineering book series (LNME)


Critical equipment of nuclear power plants and petrochemical industries is sometimes subjected to both creep and fatigue loading simultaneously. Under combined creep–fatigue loading, the creep deformation affects the fatigue behavior of the material depending on the relative duration of stress relaxation due to creep within service life. In the present paper, evaluation of creep and fatigue damage is carried out for a process reactor using elastic analysis method of ASME-NH code. The reactor material is 2.25Cr-1Mo steel. The stress evaluations are carried out at outlet nozzle where stresses are observed to be maximum. Effect of three parameters, that is, the maximum hold temperature, the duration of hold time at highest temperature and the rate of temperature change on combined creep–fatigue damage, is studied. This work provides guidelines for performing creep–fatigue analysis for similar pressure components.


ASME-NH Creep–fatigue interaction Creep ratcheting 2.25Cr-1Mo steel 



Total creep–fatigue damage


Local geometric concentration factor


Stress ratio factor at yield


Factor for reduction in extreme fiber bending stress due to effect of creep


Multiaxial plasticity and Poisson ratio adjustment factor


Primary bending equivalent stress


Local primary membrane equivalent stress


Primary membrane equivalent stress


Maximum secondary stress range

S*, \( \bar{S} \)

Stress indicators


Alternating stress intensity


Initial stress


Allowable stress


Hot relaxation strength


Temperature and time-dependent stress intensity limit


Yield strength of material


Primary stress parameter


Secondary stress parameter


Dimensionless effective creep stress parameter


Maximum equivalent strain range


Modified maximum equivalent strain range


Creep strain increment


Total strain range


Effective creep stress


Duration of time interval


  1. 1.
    Plumbridge WJ, Dean M, Sand Miller DA (1982) The importance of failure mode in fatigue-creep interactions. In: Fatigue of engineering materials and structures, vol 5, pp 101–114Google Scholar
  2. 2.
    Hormozi R, Biglari F, Nikbin K (2015) Experimental and numerical creep-fatigue study of type 316 stainless steel failure under high-temperature LCF loading condition with different hold time. Eng Fract Mech 141:19–43CrossRefGoogle Scholar
  3. 3.
    Jawad MH, Jetter RI (2009) “Creep-fatigue analysis” in design and analysis of ASME Boiler and pressure vessel components in the creep range. ASME Press, New York, pp 151–176Google Scholar
  4. 4.
    Koo GH, Yoo B (2000) Elevated temperature design of KALIMER internals accounting for creep and rupture effects. J Korean Nucl Soc, vol 32, pp 66–594Google Scholar
  5. 5.
    Gurumurthy K, Balaji S et al (2014) Creep-fatigue design studies for process reactor components subjected to elevated temperature service as per ASME-NH. Procedia Eng 86:327–334CrossRefGoogle Scholar
  6. 6.
    Fournier B, Sauzay M et al (2008) Creep-fatigue oxidation interactions in 9Cr-1Mo martensitic steel. Part III: lifetime prediction. Int J Fatigue 30:1797–1812CrossRefGoogle Scholar
  7. 7.
    AFCEN (2002) Design and construction rules for mechanical components of FBR Nuclear Islands. RCC-MR, 2002 edn. AFCENGoogle Scholar
  8. 8.
    Oldham J, Abou-Hanna J (2011) Numerical investigation of creep-fatigue life prediction utilizing hysteresis energy as a damage parameter. Int J Pressure Vessels Piping 88:149–157CrossRefGoogle Scholar
  9. 9.
    ASME Boiler and Pressure Vessel Code (2015) Section III, Subsection NHGoogle Scholar
  10. 10.
    Manson SS, Halford GR (2009) Fatigue and durability of metals at high temperatures. ASM International, Materials Park, OhioGoogle Scholar
  11. 11.
    Guodong ZB, Yanfen Z et al (2011) Creep-fatigue interaction damage model and its application in modified 9Cr–1Mo steel. Nucl Eng Des 241:4856–4861CrossRefGoogle Scholar
  12. 12.
    Fan ZC, Chen XD et al (2009) A CDM-based study of fatigue-creep interaction behavior. Int J Pressure Vessels Piping 86:628–632CrossRefGoogle Scholar
  13. 13.
    Aoto K, Komine R et al (1994) Creep-fatigue evaluation of normalized and tempered modified 9Cr-1Mo. Nucl Eng Des 153:97–110CrossRefGoogle Scholar
  14. 14.
    ASME Boiler and Pressure Vessel Code (2015) Section VIII, Division 1Google Scholar
  15. 15.
    ANSYS Workbench (2015) Release 14.5, ANSYS Inc.Google Scholar
  16. 16.
    ASME Boiler and Pressure Vessel Code (2015) Section II, Part DGoogle Scholar
  17. 17.
    ASME Boiler and Pressure Vessel Code (2015) Section VIII, Division 2 Google Scholar
  18. 18.
    Koo GH, Lee JH (2006) High-temperature structural integrity evaluation method and application studies by ASME-NH for the next generation reactor design. J Mech Sci Technol 20:2061–2078CrossRefGoogle Scholar

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© Springer Nature Singapore Pte Ltd. 2018

Authors and Affiliations

  1. 1.Mechanical Engineering DepartmentSardar Patel College of EngineeringMumbaiIndia

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