0
Research Papers: Materials and Fabrication

Development of Creep–Fatigue Evaluation Method for 316FR Stainless Steel

[+] Author and Article Information
Yuji Nagae

Japan Atomic Energy Agency,
4002 Narita,
O-arai, Ibaraki 311-1393, Japan
e-mail: nagae.yuji@jaea.go.jp

Shigeru Takaya, Tai Asayama

Japan Atomic Energy Agency,
4002 Narita,
O-arai, Ibaraki 311-1393, Japan

1Corresponding author.

Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received June 27, 2014; final manuscript received August 25, 2014; published online February 20, 2015. Assoc. Editor: Marina Ruggles-Wrenn.

J. Pressure Vessel Technol 137(4), 041407 (Aug 01, 2015) (5 pages) Paper No: PVT-14-1096; doi: 10.1115/1.4028497 History: Received June 27, 2014; Revised August 25, 2014; Online February 20, 2015

In the design of fast reactor plants, the most important failure mode to be prevented is creep–fatigue damage at elevated temperatures. 316FR stainless steel is a candidate material for the reactor vessel and internal structures of such plants. The development of a procedure for evaluating creep–fatigue life is essential. The method for evaluating creep–fatigue life implemented in the Japan Society of Mechanical Engineers code is based on the time fraction rule for evaluating creep damage. Equations such as the fatigue curve, dynamic stress–strain curve, creep rupture curve, and creep strain curve are necessary for calculating creep–fatigue life. These equations are provided in this paper and the predicted creep–fatigue life for 316FR stainless steel is compared with experimental data. For the evaluation of creep–fatigue life, the longest time to failure is about 100,000 h. The creep–fatigue life is predicted to an accuracy that is within a factor of 2 even in the case with the longest time to failure. Furthermore, the proposed method is compared with the ductility exhaustion method to investigate whether the proposed method gives conservative predictions. Finally, a procedure based on the time fraction rule for the evaluation of creep–fatigue life is proposed for 316FR stainless steel.

FIGURES IN THIS ARTICLE
<>
Copyright © 2015 by ASME
Your Session has timed out. Please sign back in to continue.

References

Asada, Y., Ueta, M., Kanaoka, T., Sukekawa, M., and Nishida, T., 1992, “Current Status of the Development of Advanced 316-steel for FBR Structures, Stress Classification, Robust Methods, and Elevated Temperature Design,” PVP-Vol.230, Stress Classification, Robust Methods, and Elevated Temperature Design, edited by Becht IV, C., Seshadri, R., Marriott, D., Book No. G00665, ASME, pp. 61–65.
Nakazawa, T., Kimura, H., Kimura, K., and Kaguchi, H., 2003, “Advanced Type Stainless Steel 316FR for Fast Breeder Reactor Structures,” J. Mater. Process. Technol., 143–144(2), pp. 905–909. [CrossRef]
Nakazawa, T., Kimura, H., Tendo, M., and Komatsu, H., 2000, “Effects of Carbon, Molybdenum, and Phosphorus Contents on Creep Rupture Properties of Low Carbon Medium Nitrogen Type 316 Stainless Steel,” J. Jpn. Inst. Met., 64(2), pp. 926–933 (in Japanese).
Japan Society of Mechanical Engineers, 2012, Code for Nuclear Power Generation Facilities, Rules on Design and Construction for Nuclear Power Plants, Section II Fast Reactor Standards, Japan Society of Mechanical Engineers, Saporro, Japan, (in Japanese).
Odaka, S., Kato, S., Yoshida, E., Kawakami, T., Suzuki, T., Kawashima, S., and Ishigami, K., 2005, “Material Test Data of 316FR Steel (IX),” Report No. JNC TN9450 2005-001 (in Japanese).
Takahashi, Y., Shibamoto, H., and Inoue, K., 2008, “Study on Creep–Fatigue Life Prediction Methods for Low-Carbon Nitrogen-Controlled 316 Stainless Steel (316FR),” Nucl. Eng. Des., 238(2), pp. 322–335. [CrossRef]
Takahashi, Y., Shibamoto, H., and Inoue, K., 2008, “Long-Term Creep Rupture Behavior of Smoothed and Notched Bar Specimens of Low-Carbon Nitrogen-Controlled 316 Stainless Steel (316FR) and Their Evaluation,” Nucl. Eng. Des., 238(2), pp. 310–321. [CrossRef]
Date, S., and Otani, T., 2008, “Long Term Creep–Fatigue Behavior and Fracture Morphology of 316FR Developed for FBR,” Proceedings of the 46th Symposium on Strength of Materials at High Temperatures, Dec. 4–5, pp. 43–47.
Onizawa, T., Nagae, Y., Takaya, S., and Asayama, T., 2013, “Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors (2) Development of the Material Strength Standard of 316FR Stainless Steel,” ASME Paper No. PVP2013-97608. [CrossRef]
Takahashi, Y., Date, S., and Nakazawa, T., 1997, “Effect of Grain Size on High Temperature Strength of Fast Reactor Spec.SUS316,” J. Soc. Mater. Sci. Jpn., 46(11), pp. 1274–1279. [CrossRef]
Sauzay, M., Mottot, M., Allais, L., Noblecourt, M., Monnet, I., and Perinet, J., 2004, “Creep–Fatigue Behavior of an AISI Stainless Steel at 550 Degree C,” Nucl. Eng. Des., 232(3), pp. 219–236. [CrossRef]
Kim, D. W., Chang, J.-H., and Ryu, W.-S., 2008, “Evaluation of the Creep–Fatigue Damage Mechanism of Type 316L and Type 316LN Stainless Steel,” Int. J. Pressure Vessels Piping, 85(6), pp. 378–384. [CrossRef]
Aoto, K., Komine, R., Ueno, F., Kawasaki, H., and Wada, Y., 1994, “Creep–Fatigue Evaluation of Normalized and Tempered Modified 9Cr-1Mo,” Nucl. Eng. Des., 153(1), pp. 97–110. [CrossRef]
Takahashi, Y., Dogan, B., and Gandy, D., 2009, “Systematic Evaluation of Creep–Fatigue Life Prediction Methods for Various Alloys,” ASME Paper No. PVP2009-77990. [CrossRef]
British Energy Generation Ltd., 2003, An Assessment Procedure for the High Temperature Response of Structures, R5 Issue 3, by R. A.Ainsworth, ed., British Energy Generation Ltd., UK.

Figures

Grahic Jump Location
Fig. 1

Fatigue curve at 823 K

Grahic Jump Location
Fig. 2

Creep rupture curves

Grahic Jump Location
Fig. 3

Change in peak stress with increasing number of cycles

Grahic Jump Location
Fig. 4

Effect of time per cycle on stress range at 823 K

Grahic Jump Location
Fig. 5

Cyclic stress–strain curves at 823 K

Grahic Jump Location
Fig. 6

Comparison of predicted life with observed life

Grahic Jump Location
Fig. 7

Accumulated damages at failure

Grahic Jump Location
Fig. 8

Predictability of creep–fatigue life in long-term region

Grahic Jump Location
Fig. 9

Example of stress relaxation curve in low strain range

Grahic Jump Location
Fig. 10

Comparison of predicted life by ductility exhaustion approach and time fraction rule

Tables

Errata

Discussions

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In