The role of dynamic strain-ageing in the environment assisted cracking observed in pressure vessel steels

Fatigue and Fracture of Engineering Materials and Structures

Volumn 20, Issue 1, 1997, Pages 1-12

  Atkinson, J D ^a   Yu, J ^a  

^a SHEFFIELD HALLAM UNIVERSITY   (United Kingdom)

Author keywords

A533B Class 1 steel; Dynamic strain ageing; Environment assisted cracking; Strain rate and temperature effects

Indexed keywords

ACTIVATION ENERGY; AGING OF MATERIALS; CRACK INITIATION; DUCTILITY; HARDENING; MECHANICAL TESTING; NITROGEN; PRESSURE VESSELS; STRAIN RATE; STRENGTHENING (METAL); STRESSES; THERMAL EFFECTS;

DYNAMIC STRAIN AGEING BEHAVIOUR; ENVIRONMENT ASSISTED CRACKING; REACTOR PRESSURE VESSEL;

STEEL;

EID: 0030695692     PISSN: 8756758X     EISSN: None     Source Type: Journal    
DOI: 10.1111/j.1460-2695.1997.tb00396.x     Document Type: Article

References (36)

1. J. D. Atkinson, Z-Y. Chen and J. Yu (1995) A predictive model for corrosion fatigue crack growth rates in RPV steels exposed to PWR environments. In: Fatigue and Crack Growth: Environmental Effects, Modelling Studies, and Design Considerations (Edited by S. Yukawa), PVP, Vol. 306, pp. 3-8. ASME, New York.
2. J. D. Atkinson and Z-Y. Chen (1993) The effect of temperature on corrosion fatigue crack propagation in reactor pressure vessel steels. Proceedings of 6th International Symposium on Environmental Degradation of Materials in Nuclear Power System, Water Reactors, 1-5 August, San Diego, California, USA.
3. Y. Katada and N. Nagata (1985) The effect of temperature on fatigue crack growth behaviour of a low alloy pressure vessel steel in a simulated BWR environment. Corros. Sci. 25(8/9), 693-704.
4. W. H. Cullen (1983) Effect of temperature on fatigue crack growth of A508-2 in LWR environment. In: Thermal and Environmental Effects in Fatigue: Research-Design Interface (Edited by C. E. Jaske, S. J. Hudak and M. E. Mayfield), PVP, Vol. 71, pp. 231-241. Book No. H00257, ASME.
5. D. R. Tice, I. Bramwell and J. D. Atkinson (1995) Results of an international collaborative programme examining the effects of temperature on corrosion fatigue crack growth of reactor pressure vessel steels. Paper presented at International Symposium on Plant Ageing and Life Prediction of Corrodible Structures, 15-18 May, Hokhadi University, Sapporo, Japan.
6. J. D. Atkinson and J. E. Forrest (1985) Factors influencing the rate of growth of fatigue cracks in RPV steels exposed to a simulated PWR primary water environment. Corros. Sci. 25(8/9), 607-631.
7. J. D. Atkinson (1989) The effect of corrosion potential on fatigue crack growth rates in a pressure vessel steel exposed to PWR primary water environments. Proceedings of the Fourth International Symposium on Environment Degradation of Materials in Nuclear Power Systems-Water Reactors (Edited by Cubicciotti), 6-10 August, Jekyll Island, Georgia, USA.
8. G. Sound and M. Trolle (1990) The influence of oxygen and sulphate contents of the water on the tendency to stress corrosion cracking in pressure vessel steels at 288°C. Proceedings of the Third International Atomic Energy Agency Specialists' Meeting on Subcritical Crack Growth, 14-17 May, Moscow, USSR, Session 2, pp. 3-8.
9. T. Shoji (1990) The critical cracking potential of reactor pressure vessel steels in pressurised high temperature water, ibid. Session 2, pp. 109-116.
10. J. Congleton, T. Shoji and R. N. Parkins (1985) The stress corrosion cracking of reactor pressure vessel steel in high temperature water. Corros. Sci. 25(8/9), 633-650.
11. K. Rippstein and H. Kaesche (1989) The stress corrosion of a reactor pressure vessel steel in high temperature water at high flow rates. Corros. Sci. 29(5), 517-534.
12. F. P. Ford and P. I. Andresen (1990) Corrosion fatigue of A533B/A508 pressure vessel steels in 288°C water. Proceedings of the Third International Atomic Energy Agency Specialists' Meeting on Subcritical Crack Growth, 14-17 May, Moscow, USSR, Session 1, pp. 105-124.
13. F. P. Ford (1985) Overview of collaborative research into the mechanisms of environmentally controlled cracking in the low alloy pressure vessel steel/water system. Proceedings of the Second International Atomic Energy Agency Specialists' Meeting on Subcritical Crack Growth (Edited by W. H. Cullen), 15-17 May, Sendai, Japan, Session 3, pp. 3-72.
14. F. P. Ford and P. Combrade (1985) Electrochemical reaction rates on bare surfaces and their use in a crack prediction model for the low-alloy steel water system. ibid. Session 3, pp. 231-268.
15. J. Congleton and R. N. Parkins (1987) Stress corrosion cracking of steel in high temperature water. Corrosion 87, 9-13 March, Moscone Centre/San Francisco, California, USA.
16. J. D. Atkinson, J. Yu and Z-Y. Chen (1994) An analysis of the effects of sulphur content and potential on corrosion fatigue crack growth in reactor pressure vessel steels. Proceedings of International Conference on Environment Sensitive Fracture of Structural and Engineering Materials, 6-9 September 1994, Guilin, China, pp. 268-280.
17. J. H. Bulloch and J. D. Atkinson (1992) An assessment of the influence of sulphide distribution in the promotion on environmentally assisted crack growth in ferritic pressure vessel steels. Proceedings of 18th MPA-Seminar, 8-9 October, Stuttgart, Germany, paper no. 29.
18. P. Combrade, P. Marcus and G. Slama (1989) On the role of sulphur on the dissolution of pressure vessel steels at the tip of a propagating crack in PWR environment. Proceedings of 4th Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 6-10 August, Jekyll Island, USA, 8/48-8/62.
19. H. Hanninen, M. Kempainen and K. Torronen (1988) The role of inclusions in corrosion fatigue crack growth of pressure vessel steels in high temperature reactor water. Proceedings of Symposium on Inclusions and their influence on Material Behaviour in Conjunction with the 1988 World Materials Congress, 24-30 September, Chicago, Illinois, USA, pp. 157-172.
20. J. D. Atkinson and J. E. Forrest (1985) The role of MnS inclusions in the development of environmentally assisted cracking of nuclear reactor pressure vessel steels. Proceedings of the Second International Atomic Energy Agency Specialists' Meeting on Subcritical Crack Growth (Edited by W. H. Cullen), 15-17 May, Sendai, Japan, Sessions 3 and 5, pp. 153-178.
21. W. H. Cullen, M. Kempainen, H. Hanninen and K. Torronen (1985) The effects of sulphur chemistry and flow rate on fatigue crack growth rates in LWR environments, US Nuclear Regulatory Commission Report, NUREG/CR-4121, MEA-2053.
22. H. Hanninen, K. Torronen, M. Kempainen and S. Salonen (1983) On the mechanisms of environment sensitive cyclic crack growth of nuclear reactor pressure vessel steels. Corros. Sci. 23(6), 663-679.
23. I. S. Kim and S. S. Kang (1995) Dynamic strain-ageing in SA508-Class-3 pressure-vessel steel. Int. J. Pressure Vessel Steel 62(2), 123-129.
24. S. S. Kang and I. S. Kim (1992) Dynamic strain-ageing effect on fracture-toughness of vessel steels. Nuclear Tech. 97(3), 336-343.
25. E. A. Little and J. A. Hudson (1985) The dynamic strain ageing of A533B class 1 nuclear pressure vessel steel. UKAEA Report, AERE-R11485, Harwell.
26. P. S. Godavarti, Y. H. Jung, R. T. Odierno and K. L. Murty (1987) Synergistic effects of dynamic strainageing and irradiation on mechanical and fracture properties of ferritic steels. Proceedings of Third International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 30 August-3 September, Traverse City, MI.
27. B. Ostensson (1977) The fracture toughness of pressure vessel steel at elevated temperatures. IAEA-Sm-218/17, pp. 303-315.
28. B. Houssin, G. Slama and P. Moulin (1979) Strain ageing sensitivity of pressure vessel steels and welds of nuclear reactor components. In: Assuring Structural Integrity of Steel Reactor Pressure Vessels (Edited by L. E. Steele and K. E. Stahlkopf), pp. 57-67. Applied Science Publishers Ltd., London.
29. B. J. Brindley (1970) The effect of dynamic strain-ageing on the ductile fracture process in mild steel. Acta Metall. 18, March, 325-329.
30. E. A. Little and D. R. Harris (1970) The correlation of radiation-hardening with interstitial nitrogen content in mild steels. Met. Sci. J. 4, 195-200.
31. A. S. Keh, Y. Nakada and W. C. Leslie (1968) Dynamic strain ageing in iron and steel. In: Dislocation Dynamics (Edited by A. R. Rosenfield and G. T. Hahn), pp. 381-408.
32. S. L. Mannan (1993) Role of dynamic strain-ageing in low-cycle fatigue. Bull. Mater. Sci. 16(6), 561-682.
33. M. Weisse, C. K. Wamukwamba, H. J. Christ and H. Mughrabi (1993) The cyclic deformation and fatigue behaviour of the low-carbon steel SAE-1045 in the temperature regime of dynamic strain ageing. Acta Metall. et Mater. 41(7), 2227-2233.
34. G. P. Karzov, B. T. Timofeev and Y. G. Filchagin (1993) The influence of prolonged exposure to operating temperatures and strain ageing on the material properties of nuclear-power plant reactor vessels and pipings. Int. J. Pressure Vessels Piping 53(2), 195-216.
35. J. D. Penrose and A. F. Brown (1971) Role of impurity in serrated-yielding processes in iron. J. Iron Steel Institute, November, 862-868.
36. J. A. H. Huit and F. A. McClintock (1956) Elastic plastic stress and strain distributions around sharp notches under repeated shear. Proceedings of the 9th International Congress on Applied Mechanics, Brussels, pp. 51-58.