journal article·2013-10

Environmental effect on fatigue strength of stainless steel in PWR primary water – Role of crack growth acceleration in fatigue life reduction

Masayuki Kamaya

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Abstract

Abstract The influence of the pressurized water reactor (PWR) water environment on fatigue life and fatigue crack growth rate was discussed. The fatigue lives of Type 316 stainless steel in the PWR water environment were investigated using cylindrical hollow specimens. The acceleration in the crack growth due to the environment was quantified by investigating spacing of striations and crack growth tests using compact tension specimens. The growth rates obtained could be represented by the strain intensity factor. It was shown that the fatigue lives estimated by crack growth prediction agreed with those obtained by the tests. Then, it was concluded that the reduction in the fatigue life due to the PWR water environment was brought about not by enhancement of crack initiation but by the acceleration of the crack growth.
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Research context

OpenAlex topics: Fatigue and fracture mechanics · Fire effects on concrete materials · Material Properties and Failure Mechanisms

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References (29)

Show source-provided references
1. Higuchi M. Comparison of environmental fatigue evaluation methods in LWR water. In: Proceedings of ASME 2008 pressure vessels and piping conference. Paper no. 61087; 2008.10.1115/PVP2008-61087 ↗
2. Chopra OK, Shack WJ. Effect of LWR coolant environments on the fatigue life of reactor materials. NUREG/CR-6909, ANL-06/08, USA, 2007.10.1115/PVP2006-ICPVT-11-93889 ↗
3. De Baglion L, Mendez J, Le Duff JA, Lefrancois A. Influence of PWR primary water on LCF behavior of type 304L austenitic stainless steel at 300 degrees C: comparison with results obtained in vacuum or in air. In: Proceedings of ASME 2012 pressure vessels and piping conference. Paper no. 78767; 2012.10.1115/PVP2012-78767 ↗
4. Solomon HD, Amzallag C, Vallee AJ, DeLair RE. 107 Cycle fatigue limit of type 304L SS in air and PWR water, at 150°C and 300°C. In: Proceedings of the 12th international conference on environmental degradation of materials in nuclear power system; 2005. p. 1083–9.
5. Sakaguchi K, Nomura Y, Suzuki S, Kanasaki H. Applicability of the modified rate approach method under various conditions simulating actual plant conditions. In: Proceedings of ASME 2006 pressure vessels and piping conference. Paper no. 93220; 2006.10.1115/PVP2006-ICPVT-11-93220 ↗
6. Higuchi M, Sakaguchi K, Hirano A, Nomura Y. Final proposal of environmental fatigue life correction factor (Fen) for structural materials in LWR water environment. In: Proceedings of ASME 2007 pressure vessels and piping conference. Paper no. 26100; 2007.10.1115/PVP2007-26100 ↗
7. Huin N, Tsutsumi K, Legras L, Couvant T, Loisnard D, Mendez J, et al. Fatigue crack initiation of 304L stainless steel in simulated PWR primary environment: relative effect of strain rate. In: Proceedings of ASME 2012 pressure vessels and piping conference. Paper no. 78340; 2012.10.1115/PVP2012-78340 ↗
8. Japan Society Mechanical Engineers. Codes for nuclear power generation facilities: environmental fatigue evaluation method for nuclear power plants. JSME S NF1-2006; 2006.
9. ASME. Rules for construction of nuclear facility components – ASME boiler and pressure vessel code section III Code case N-792: fatigue evaluations including environmental effects, ASME; 2010.
10. Solin J, Karjalainen-Roikonen P, Arilahti E, Moilanen P. Low cycle fatigue behaviour of 316NG alloy in PWR environment. In: Proceedings of 3rd international conference on fatigue of reactor components, Seville; 2004.
11. Solomon HD, Amzallag C, Vallee AJ, De Lair RE. Influence of mean stress on the fatigue behavior of 304L SS in air and PWR water. In: Proceedings of ASME 2005 pressure vessels and piping conference. Paper no. 71064; 2005.10.1115/PVP2005-71064 ↗
12. What is fatigue damage? A view point from the observation of low cycle fatigue process10.1016/j.ijfatigue.2004.10.009 ↗
13. Fatigue properties of 316 stainless steel and its failure due to internal cracks in low-cycle and extremely low-cycle fatigue regimes10.1016/j.ijfatigue.2009.12.003 ↗
14. Fatigue life prediction of stainless steel under variable loading (damage factors determining fatigue life and damage evaluation for two-step test)10.2472/jsms.60.871 ↗
15. Strain-based modeling of fatigue crack growth – an experimental approach for stainless steel10.1016/j.ijfatigue.2012.05.006 ↗
16. Standard test method for measurement of fatigue crack growth rates. ASTM E647-00; 2000.
17. Fatigue design criteria for pressure vessel alloys10.1115/1.3454577 ↗
18. ASME. Rules for construction of nuclear facility components – ASME boiler and pressure vessel code section III. ASME, New York; 2010.
19. Japan Society Mechanical Engineers. Codes for nuclear power generation facilities: rules of fitness-for-service for nuclear power plants. JSME S NA1-2008; 2008.
20. Fatigue microcracks in type 304 stainless steel at elevated temperature10.1111/j.1460-2695.1990.tb00619.x ↗
21. Initiation of fatigue cracks in commercial aluminum alloys and the subsequent propagation of very short cracks10.1016/0013-7944(75)90004-1 ↗
22. Physically short crack propagation in metals during high cycle fatigue10.1016/j.ijfatigue.2009.03.002 ↗
23. Cyclic deformation of ferritic steel – II. Stage II crack propagation10.1016/0956-7151(91)90142-N ↗
24. Murakami · 1987 · vol. 2
25. Kitagawa H, Takahashi S, Suh CM, Miyashita S. Quantitative analysis of fatigue process – microcracks and slip lines under cyclic strains, vol. 675. ASTM STP; 1979: p. 420–49.10.1520/STP35901S ↗
26. A strain intensity approach to high temperature fatigue crack growth and failure10.1016/0025-5416(78)90203-3 ↗
27. Damage assessment of low-cycle fatigue by crack growth prediction (development of growth prediction model and its application)10.1299/kikaia.78.1518 ↗
28. Chapuliot S. Formulaire de KI pour les tubes comportant un defaut de surface semi-elliptique longitudinal ou circonferentiel, interne ou externe. Rapport CEA-R-5900; 2000.
29. Nomura Y, Tsutsumi K, Kanasaki H, Chigusa N, Jotaki K, Shimizu H, Hirose T, Ohata H. Fatigue crack growth curve for austenitic stainless steels in PWR environment. In: Proceedings of ASME 2004 pressure vessels and piping conference. PVP-vol. 480; 2004: p. 63–70.10.1115/PVP2004-2674 ↗