Fatigue design method for 2.25Cr-1Mo-V steel reactors in code case 2605 (CC 2605) is reviewed. Main factors such as the accelerating function of fatigue action, the cyclic frequency, the strain damage factor (β) 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 a value of around 200 MPa (slightly dependent on temperature) for the adjusted uniaxial Omega damage parameter and 16 MPa for the creep strain rate when the Omega creep-damage method is employed.
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April 2018
Research-Article
On Fatigue Design Curves for 2.25Cr-1Mo-V Steel Reactors at Elevated Temperature in Code Case 2605
Jian-Guo Gong,
Jian-Guo Gong
School of Mechanical and Power Engineering,
East China University of
Science and Technology,
130 Meilong Road,
Shanghai 200237, China
e-mail: jggong@ecust.edu.cn
East China University of
Science and Technology,
130 Meilong Road,
Shanghai 200237, China
e-mail: jggong@ecust.edu.cn
Search for other works by this author on:
Fang Liu,
Fang Liu
School of Mechanical and Power Engineering,
East China University of
Science and Technology,
Shanghai 200237, China
e-mail: 1107937101@qq.com
East China University of
Science and Technology,
130 Meilong Road
,Shanghai 200237, China
e-mail: 1107937101@qq.com
Search for other works by this author on:
Fu-Zhen Xuan
Fu-Zhen Xuan
School of Mechanical and Power Engineering,
East China University of
Science and Technology,
Shanghai 200237, China
e-mail: fzxuan@ecust.edu.cn
East China University of
Science and Technology,
130 Meilong Road
,Shanghai 200237, China
e-mail: fzxuan@ecust.edu.cn
Search for other works by this author on:
Jian-Guo Gong
School of Mechanical and Power Engineering,
East China University of
Science and Technology,
130 Meilong Road,
Shanghai 200237, China
e-mail: jggong@ecust.edu.cn
East China University of
Science and Technology,
130 Meilong Road,
Shanghai 200237, China
e-mail: jggong@ecust.edu.cn
Fang Liu
School of Mechanical and Power Engineering,
East China University of
Science and Technology,
Shanghai 200237, China
e-mail: 1107937101@qq.com
East China University of
Science and Technology,
130 Meilong Road
,Shanghai 200237, China
e-mail: 1107937101@qq.com
Fu-Zhen Xuan
School of Mechanical and Power Engineering,
East China University of
Science and Technology,
Shanghai 200237, China
e-mail: fzxuan@ecust.edu.cn
East China University of
Science and Technology,
130 Meilong Road
,Shanghai 200237, China
e-mail: fzxuan@ecust.edu.cn
1Corresponding author.
Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received August 15, 2017; final manuscript received December 18, 2017; published online January 24, 2018. Assoc. Editor: Kiminobu Hojo.
J. Pressure Vessel Technol. Apr 2018, 140(2): 021101 (10 pages)
Published Online: January 24, 2018
Article history
Received:
August 15, 2017
Revised:
December 18, 2017
Citation
Gong, J., Liu, F., and Xuan, F. (January 24, 2018). "On Fatigue Design Curves for 2.25Cr-1Mo-V Steel Reactors at Elevated Temperature in Code Case 2605." ASME. J. Pressure Vessel Technol. April 2018; 140(2): 021101. https://doi.org/10.1115/1.4038903
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