0
Research Papers: Materials and Fabrication

Experimental and Analytical Studies on the Effect of Excessive Loading on Fatigue Crack Propagation in Piping Materials

[+] Author and Article Information
Kunio Onizawa

Nuclear Safety Research Center,
Japan Atomic Energy Agency,
Tokai, Ibaraki 319-1195, Japan

Yinsheng Li

Japan Nuclear Energy Safety Organization,
Minato-ku, Tokyo 105-0001, Japan

Genki Yagawa

Center for Computational Mechanics Research,
Toyo University,
Bunkyo-ku, Tokyo 112-0001, Japan

Contributed by the Pressure Vessel and Piping Division of ASME for publication in the Journal of Pressure Vessel Technology. Manuscript received November 18, 2012; final manuscript received April 11, 2013; published online June 11, 2013. Assoc. Editor: Kunio Hasegawa.

J. Pressure Vessel Technol 135(4), 041406 (Jun 11, 2013) (9 pages) Paper No: PVT-12-1170; doi: 10.1115/1.4024454 History: Received November 18, 2012; Revised April 11, 2013

The seismic design review guide in Japan was revised in September 2006 to address the occurrence of a large earthquake beyond the design basis. In addition, Japanese nuclear power plants (NPPs) experienced multiple large earthquakes, such as Niigata-ken Chuetsu-Oki Earthquake in 2007 and the Great East Japan Earthquake in 2011. Therefore, it is very important to assess the structural integrity of reactor piping under such a large earthquake when a crack exists in the piping. In this work, crack growth behavior after excessive loading during the large-scale earthquake were experimentally and analytically evaluated for carbon steel and austenitic stainless steel. Some cyclic loading patterns with increasing and decreasing load amplitudes and maximum loads were applied to fatigue crack growth test specimens. From the results, the retardation of crack growth rate was clearly observed after excessive loading. In addition, the applicability to the retardation effect of the modified Wheeler model was confirmed. It is also concluded that the retardation effect has little influence on the failure probability due to seismic loading using probabilistic fracture mechanics (PFM) analyses with the modified Wheeler model.

Copyright © 2013 by ASME
Your Session has timed out. Please sign back in to continue.

References

Olson, R. J., Darlaston, B. J., Mayfield, M. E., and Schmidt, R. A., 1993, “The IPIRG Dynamic Pipe Loop Test Facility,” Nucl. Eng. Des., 144(1), pp. 77–90. [CrossRef]
Scott, P., Olson, R., Bockbrader, J., Wilson, M., Gruen, B., Morbitzer, R., Yang, Y., Williams, C., Brust, F., Fredette, L., Ghadiali, N., Wilkowski, G., Rudland, D., Feng, Z., Wolterman, R., and Greene, C. A., 2005, “The Battelle Integrity of Nuclear Piping (BINP) Program Final Report, Summary and Implications of Results,” Report No. NUREG/CR-6837.
Olson, R., Wolterman, R., Scott, P., Krishnaswamy, P., and Wilkowski, G., 1994, “The Next Generation Analysis Methodology for Cracked Pipe Systems Subjected to Dynamic Loading, PVP-Vol.275-1,” Seism. Eng.1(1), pp. 159–172.
Miyazaki, K., Kanno, S., Hayashi, M., Ishiwata, M., Gotoh, N., Miura, N., Fujioka, T., and Kashima, K., 1996, “Fracture Behavior Under Monotonic and Low Cycle Loading in Carbon Steel Pipes and Welded Pipe Joints With a Defect, PVP-Vol. 323,” Fatigue Fract., 1, pp. 241–248.
Miura, N., 2001, “Evaluation of Crack Opening Behavior for Cracked Pipes—Development of Crack Opening Evaluation Method in Consideration of Restraint,” CRIEPI Report No. T00006.
Hasegawa, K., Sakata, K., Miyazaki, K., and Kanno, S., 2002, “Fatigue Strength for Pipes With Allowable Flaws and Design Fatigue Curve,” Int. J. Pressure Vessels Piping, 79, pp. 37–44. [CrossRef]
Shiratori, M., Yakura, M., Karasawa, T., Nakamura, I., and Otani, A., 2000, “Failure Analysis of Degraded Piping Against Seismic Loading,” Proceeding of 2000 ASME Pressure Vessels and Piping Conference, PVP-Vol. 402-1 Seismic Engineering-2000, Vol. 1, pp. 37–48.
Nakamura, I., Ogawa, N., Otani, A., and Shiratori, M., 2000, “An Experimetal Study on Dynamic Behavior of Piping Systems With Local Degradation,” Presented at the 2000 ASME Pressure Vessels and Piping Conference, PVP-Vol. 402-1 Seismic Engineering-2000, Vol. 1, pp. 15–22.
Shin, C. S., and Hsu, S. H., 1993., “On the Mechanism and Behavior of Overload Retardation in AISI 304 Stainless Steel,” Int. J. Fatigue, 15(3), pp. 181–192. [CrossRef]
Sun, Y., An, K., Tang, F., Hubbard, C. R., Lu, Y. L., Choo, H., and Liaw, P. L., 2006, “Changes in Lattice-Strain Profiles Around a Fatigue Crack Through the Retardation Period After Overloading,” Physica B, 385–386, pp. 633–635. [CrossRef]
Jono, M., Song, J., Sugeta, A., and Nawata, T., 1986, “Elastic-Plastic Fatigue Crack Growth Behavior under Repeated Two-Step Loading,” Jpn. Soc. Mech. Eng., 52(477), pp. 1257–1263. [CrossRef]
ASTM International, 2008, ASTM E1820-08, “Standard Test Method for Measurement of Fracture Toughness,” Book of Standards, Vol. 03.01, West Conshohocken, PA. [CrossRef]
ASTM International, 2000, ASTM E647-00, “Standard Test Method for Measurement of Fatigue Crack Growth Rates,” Book of Standards, Vol. 03.01, West Conshohocken, PA. [CrossRef]
Japan Society of Mechanical Engineers, 2008, Codes for Nuclear Power Generation Facilities–Rules on Fitness-for-Service for Nuclear Power Plants. Available at: http://www.jsme.or.jp/English//codes.html
Borrego, L. P., Ferreira, J. M., Pinho da Cruz, J. M., and Costa, J. M., 2003., “Evaluation of Overload Effects on Fatigue Crack Growth and Closure,” Eng. Fract. Mech., 70, pp. 1379–1397. [CrossRef]
ASTM International, 2008, ASTM E1921-08, “Standard Test Method for Measurement of Reference Temperature T0 for Ferritic Steels in the Transition Range,” Book of Standards, Vol. 03-01, West Conshohocken, PA. [CrossRef]
Wheeler, O. E., 1972., “Spectrum Loading and Crack Growth,” Trans. ASME J. Fluids Eng., 94(1), pp. 181–186 [CrossRef]
Carlson, R. L., Kardomateas, G. A., and Bates, P. R., 1991, “The Effects of Overloads in Fatigue Crack Growth,” Int. J. Fatigue, 13(6), pp. 453–460. [CrossRef]
Meggiolaro, M. A., and Castro, J. T. P., 2001, “Comparison of Load Interaction Models in Fatigue Crack Propagation,” Proceeding of COBEM 2001,” Fract. Mech. Struct. Integr., 12, pp. 247–256.
Itoh, H., Katsuyama, J., and Onizawa, K., 2008, “A Probabilistic Evaluation Model for Welding Residual Stress Distribution at Piping Joint in Probabilistic Fracture Mechanics Analysis,” Proceedings of PVP2008, ASME Pressure Vessels and Piping Division Conference, Paper No. PVP2008-61421.

Figures

Grahic Jump Location
Fig. 1

Geometry of the CT specimen used in this study

Grahic Jump Location
Fig. 2

Four loading conditions

Grahic Jump Location
Fig. 3

FEM analysis model for CT specimens

Grahic Jump Location
Fig. 4

Number of cycles versus crack length for Type 316 stainless steel, case 3: loading amplitude stepwise increase

Grahic Jump Location
Fig. 5

Number of cycles versus crack length for Type 316 stainless steel, case 4: loading amplitude stepwise decrease

Grahic Jump Location
Fig. 6

Typical behavior of crack growth subjected to amplitude decrease loading

Grahic Jump Location
Fig. 7

Determination of retardation region using the ratio of retardation value method

Grahic Jump Location
Fig. 8

Determination of retardation region using the crack growth rate as a function of crack length

Grahic Jump Location
Fig. 9

Variation of retardation region related as a function of Kb − Ka (Type 316 stainless steel)

Grahic Jump Location
Fig. 10

Schematic drawing of the relations among loading condition, plastic zone size and stress distribution during crack growth retardation

Grahic Jump Location
Fig. 11

Variation of retardation region related as a function of Kb2-Ka2

Grahic Jump Location
Fig. 12

Distribution of plastic strain obtain from FEM analysis

Grahic Jump Location
Fig. 13

Procedure for the determination of LPEMAGmin

Grahic Jump Location
Fig. 14

Variation of retardation region by FEM analysis as a function of Kb2-Ka2

Grahic Jump Location
Fig. 15

Input seismic load wave and change in range of stress intensity factor

Grahic Jump Location
Fig. 16

The result of one seismic loading on the deterministic analysis for Type 316 stainless steel

Grahic Jump Location
Fig. 17

The result of one seismic loading on the deterministic analysis for STS410 carbon steel

Grahic Jump Location
Fig. 18

The result of the PFM analysis for Type 316 stainless steel

Grahic Jump Location
Fig. 19

The result of the PFM analysis for STS410 carbon steel

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