General corrosion and stress corrosion cracking of Alloy 600 in light water reactor primary coolants
Source abstract
Abstract
Abstract The general corrosion and stress corrosion cracking behaviors of the nickel-base Alloy 600 in the primary high temperature aqueous coolants of light water cooled and moderated nuclear power reactors are reviewed. The compatible welding Alloys 182 and 82 as well as the high strength, precipitation hardened analogue, Alloy X-750, are also included. The emphasis is on what is known of the underlying science of these degradation phenomena rather than on the associated engineering consequences and remedies.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Nuclear Materials and Properties · High Temperature Alloys and Creep
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (100+)
Show source-provided references
1. Scott · 2011
2. Ford · 2015
3. Effects of BWR coolant chemistry on propensity for IGSCC initiation and growth in creviced reactor internals components
4. Fabrication and operating history considerations relative to SCC susceptibility of BWR components
5. Corrosion in boiling water reactors, ASM handbook, volume 13C
6. F. N. Speller award lecture: stress corrosion cracking in pressurized water reactors - interpretation, modeling, and remedies10.5006/1.3280580 ↗
7. Scott · 2006 · 362
8. Comparison of laboratory and field experience of PWSCC in Alloy 182 weld metal
9. Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors: Part 110.5006/1.3277522 ↗
10. Corrosion fissurante sous contrainte de l'Inconel dans l'eau à haute température
11. Sensitivity to stress corrosion and intergranular attack of high-nickel austenitic alloys10.5006/0010-9312-22.10.280 ↗
12. Influence of carbon and nickel content on stress corrosion cracking of austenitic stainless alloys in pure or chlorinated water at 350 °C
13. Historical review of the principal research concerning the phenomena of cracking of nickel base austenitic alloys
14. Historical views of the stress corrosion cracking of Ni base alloys – the Coriou effect
15. Scott · 2015
16. Some limitations of the linear polarization techniques in evaluating corrosion behavior10.5006/0010-9312-25.11.455 ↗
17. Electrochemical measurements of corrosion processes in a boiling water nuclear reactor10.5006/0010-9312-29.4.123 ↗
18. Oxide films formed on alloy 600 in lithiated water at 25 to 350 °C10.5006/1.3585044 ↗
19. The composition and properties of oxide films on type 304 stainless steel on exposure to lithiated water at 100-350 °C10.1016/0010-938X(91)90110-B ↗
20. Kim · 2003
21. BWR SCC mitigation experiences with hydrogen water chemistry
22. BWR field experience with Noblechem
23. Pourbaix diagrams for the ternary system of iron-chromium-nickel10.5006/1.3283945 ↗
24. Immiscibility in the Fe3O4–FeCr2O4 spinel binary10.1016/S0022-3697(03)00237-3 ↗
25. Riess · 2006
26. Crevice corrosion of austenitic alloys in high-temperature water10.5006/1.3284889 ↗
27. General corrosion of materials under simulated BWR primary water conditions10.1080/18811248.1994.9735174 ↗
28. A point defect model for anodic passive films I- film growth kinetics10.1149/1.2127591 ↗
29. The point defect model for the passive state10.1149/1.2069096 ↗
30. Oxide film growth kinetics on metals and alloys: I. Physical model10.1149/2.036306jes ↗
31. Coupling between ionic defect structure and electronic conduction in passive films on iron, chromium and iron–chromium alloys10.1016/S0013-4686(99)00423-5 ↗
32. Electrochemical study of the passive behaviour of Ni–Cr alloys in a borate solution—a mixed-conduction model approach10.1016/S0022-0728(01)00423-5 ↗
33. A mixed-conduction model for oxide films on Fe, Cr and Fe-Cr alloys in high temperature aqueous electrolytes - II Adaptation and justification of the model”10.1016/S0010-938X(02)00009-4 ↗
34. Betova · 2008
35. A mixed-conduction model for the oxidation of stainless steel in a high-temperature electrolyte; estimation of kinetic parameters of oxide layer growth and restructuring10.1149/1.1931447 ↗
36. Modelling of corrosion product release from steam generator tubes in primary water
37. The influence of thermal treatment on the chemistry and structure of grain boundaries in Inconel 60010.1007/BF02643684 ↗
38. Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals10.1016/S0022-3115(99)00075-6 ↗
39. Page · 1982
40. An evaluation of the SCC behavior of Inconel Alloy 690 weldments in a simulated BWR environment
41. Stress corrosion cracking initiation in Alloys 600 and 182
42. Effect of acceleration factors on the probability distribution of SCC initiation life of Alloys 600, 182 and 82 in high temperature and high purity water environments
43. Crack propagation in Alloys 600 and 182 in simulated BWR environment
44. Stress corrosion cracking propagation in low-strength nickel-base alloys in simulated BWR environments
45. Effects of Si on SCC of irradiated and unirradiated stainless steels and nickel alloys
46. Strasser · 2012
47. Crack propagation in Alloys 600 and 182 in simulated BWR environment
48. Effects of specific anionic impurities on environmental cracking of austenitic materials in 288 °C water
49. Effects of hydrogen on SCC growth rate of Ni alloys in BWR water
50. Alloy X-750 stress corrosion crack growth rate behavior in high temperature water
51. Effects of temperature on crack growth rate in sensitized type 304 stainless steel and alloy 60010.5006/1.3316104 ↗
52. Effects of temperature and corrosion potential on SCC
53. The effect of oxygen/temperature combinations on the stress corrosion cracking susceptibility of sensitized type 304 stainless steel in high purity water10.5006/0010-9312-35.12.569 ↗
54. Ford · 1982
55. Ford · 1982
56. The crack tip system & its relevance to the prediction of cracking in aqueous environments
57. Quantitative prediction of environmentally assisted cracking
58. Fundamental quantification of crack advance for life prediction in energy systems
59. Progress in mechanistic understanding of BWR SCC and implication to predictions of SCC growth behaviour in plants
60. Modeling of water and material chemistry effects on crack tip chemistry and resulting crack growth kinetics
61. Ford · 1987
62. Clarification of stress corrosion cracking mechanism on nickel-base alloys in steam generators for their long lifetime assurance
63. Intergranular stress corrosion cracking in steam generator tubing. testing of alloy 690 and alloy 600 tubes
64. Effects of metallurgical factors on stress corrosion cracking of Ni-base alloys in high temperature water
65. An overview of recent observations and interpretation of PWSCC in nickel base alloys in PWR primary water
66. Scott · 2006
67. An assessment of CRDM Alloy 600 reactor vessel head penetration PWSCC remedial measures
68. Environmental behaviour and weldability of Ni-base weld metals in PWRs
69. A review of weldability and SCC behaviour of Ni-base weld metals in laboratory PWR environment
70. Alloy 600 growth rate testing, In:
71. Influence of chemical composition, stress relief, and temperature on PWSCC crack initiation of Alloy 182 weld metal
72. Stress corrosion crack initiation of Alloy 182 weld metal in primary coolant – influence of chemical composition
73. Key parameters having an influence on stress corrosion cracking resistance of Alloy 182
74. Crack growth rate in the HAZ of Alloy 600/182
75. Failure analysis of the Ringhals Unit 3 EDM surfaces removed from the RPV outlet nozzle safe end weld
76. Stress corrosion crack initiation measurements of Alloy 600 in PWR primary water, Paper 203
77. Prediction of Alloy 600 component failures in PWR systems
78. Crack growth rates in thick materials of Alloy 600 and weld metals of Alloy 182 in laboratory primary water: comparison with field experience
79. Evaluation of the crack growth rate for Alloy 600 vessel penetrations in a primary water environment
80. The stress corrosion crack growth rate of alloy 600 heat affected zones exposed to high purity water
81. The effect of prior deformation on stress corrosion cracking growth rates of Alloy 600 materials in a simulated pressurized water reactor primary water10.1016/j.corsci.2007.07.012 ↗
82. Unusual cold work and strain rate effects on SCC
83. Stress corrosion crack growth in rolled Alloy 600 exposed to primary PWR environment
84. The effect of cold work and dissolved hydrogen in the stress corrosion cracking of Alloy 82 and Alloy 182 weld metal
85. Development of the crack growth rate curves for stress corrosion cracking nickel based alloys in a simulated primary water environment
86. Effect of cold work and processing orientation on stress corrosion cracking behavior of alloy 60010.5006/1.3287659 ↗
87. Degradation of high strength austenitic alloys X-750, 718 and A-286 in nuclear power systems
88. Effect of heat treatment on stress corrosion cracking resistance of high nickel alloys in high temperature water
89. Influence of surface condition on the susceptibility of Alloy X750 to crack initiation in PWR primary water
90. Evolution de la conception, de la fabrication et du montage des broches de fixation des tubes guides de grappes en Alliage X750
91. Stress corrosion cracking of Inconel alloy 600 in high temperature water-an update10.5006/1.3593950 ↗
92. Modeling of stress corrosion crack initiation on Alloy 600 in primary water of PWRs
93. Influence of surface condition on primary water stress corrosion cracking initiation of alloy 60010.5006/1.3290356 ↗
94. Environmental degradation of Alloy 600 and welded filler metal EN82 in elevated temperature aqueous environment
95. SCC initiation testing of nickel-based alloys in high temperature water
96. SCC initiation testing of alloy 600 in high temperature water
97. Stress corrosion life experience of 182 and 82 welds in French PWRs, paper 026
98. Dissimilar metal weld PWSCC initiation model refinement for XLPR Part I: a survey of alloy 82/182/132 crack initiation literature, paper 107
99. Importance of surface preparation for corrosion control in nuclear power stations
100. The effect of surface condition on primary water stress corrosion cracking initiation of alloy 600, paper 90