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research-article

On fatigue design curves for 2.25Cr-1Mo-V steel reactors at elevated temperature in Code Case 2605

[+] Author and Article Information
Jian-Guo Gong

School of Mechanical and Power Engineering, East China University of Science and Technology, 130 Meilong Road, Shanghai, 200237, China
jggong@ecust.edu.cn

Fang Liu

School of Mechanical and Power Engineering, East China University of Science and Technology, 130 Meilong Road, Shanghai, 200237, China
1107937101@qq.com

Fu-Zhen Xuan

School of Mechanical and Power Engineering, East China University of Science and Technology, 130 Meilong Road, Shanghai, 200237, China
fzxuan@ecust.edu.cn

1Corresponding author.

ASME doi:10.1115/1.4038903 History: Received August 15, 2017; Revised December 18, 2017

Abstract

Fatigue design method for 2.25Cr-1Mo-V steel reactors in Code Case 2605 (CC2605) is reviewed. Main factors such as the accelerating function of fatigue action, the cyclic frequency, the strain damage factor (ß) related to the fatigue design curves are addressed, and the applicable stress level for pure creep rupture analysis in CC 2605 is also discussed. Results indicate that, for the high loading levels, the accelerating function of fatigue action and strain damage factor contribute relatively remarkably to the fatigue design curve. The increase of cyclic frequency leads to a remarkable increase of the allowable fatigue cycle number and hence reduces the conservativeness of fatigue design curve. It should be stipulated in CC 2605 that the applicable stress level is higher than 200MPa for the adjusted uniaxial Omega damage parameter and 15MPa for the creep strain rate when the Omega creep-damage method is employed.

Copyright (c) 2017 by ASME
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