참고문헌 (38)

1. Amzallag 2002 5th Fontevraud Conference Contribution of Material Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors Stress corrosion life experience of 182 and 82 welds in French PWR 

2. Scott 2004 An Overview of Materials Degradation by Stress Corrosion in PWRs, EUROCORR 2004 

3. Bamford 959 2005 Proc. of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors Cracking of alloy 600 nozzles and welds in PWRs: review of cracking events and repair service experience 

4. Jenssen 2001 Proc. of the 10th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors Assessment of cracking in dissimilar metal welds 

5. Xu 833 2005 Proc. of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors Laboratory investigation of PWSCC of CRDM nozzle 3 and its J-Groove weld on the Davis-Besse reactor vessel head 

6. EPRI 2007 Materials Reliability Program: Review of Stress Corrosion Cracking of Alloys 182 and 82 in PWR Primary Water Service (MRP-220), Product ID 1015427 

7. Scott 2007 Proc. of the 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors Comparison of laboratory and field experience of PWSCC in Alloy 182 weld metal 

8. J. Nucl. Mater. Hwang 443 321 2013 10.1016/j.jnucmat.2013.07.032 Review of PWSCC and mitigation management strategies of Alloy 600 materials of PWRs 

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9. J. Nucl. Mater. Sennour 442 262 2013 10.1016/j.jnucmat.2013.09.002 TEM investigations on the effect of chromium content and of stress relief treatment on precipitation in Alloy 82 

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10. Weld. Int. Nishikawa 27 6 450 2013 10.1080/09507116.2012.708499 Effect of chromium content on stress corrosion cracking susceptibility of shielded metal arc weld metals for 600 type alloy in high-temperature pressurized pure water 

    

11. Guerre 1127 2011 Proc. of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors SCC crack growth rate of alloy 82 in PWR primary water conditions-effect of a thermal treatment 

12. FyFitch 5 69 2012 

13. Vaillant 2007 Proc. of the 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors A review of weldability and SCC behaviours of Ni-base weld metals in laboratory PWR environment 

14. Cassagne 1999 Proc. of the 9th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors Stress corrosion crack growth rate measurement in alloys 600 and 182 in primary water loops under constant load 

15. Chopra 2001 Effects of Alloy Chemistry, Cold Work, and Water Chemistry on Corrosion Fatigue and Stress Corrosion Cracking of Nickel Alloys and Welds, NUREG/CR-6721 

16. Andresen 2002 Stress corrosion crack growth rate behavior of Ni alloys 182 and 600 in high temperature water 

17. Int. J. Pressure Vessel Piping Kim 172 17 2019 10.1016/j.ijpvp.2019.03.009 Effects of heat treatment on mechanical properties and sensitization behavior of materials in dissimilar metal weld 

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18. ASTM Standard G108-94 2015 Standard Test Method for Electrochemical Reactivation (EPR) for Detecting Sensitization of AISI Type 304 and 304L Stainless Steels 

19. Scr. Mater. Tsai 53 505 2005 10.1016/j.scriptamat.2005.05.002 Effect of heat treatment on the sensitization of Alloy 182 weld 

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20. ASTM Standard G30-97 2016 Standard Practice for Making and Using U-Bend Stress-Corrosion Test Specimens 

21. J. Mater. Process. Technol. Bao 209 1 416 2009 10.1016/j.jmatprotec.2008.02.021 Precipitation and Cr depletion profiles of Inconel 182 during heat treatment and laser surface melting 

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22. Surf. Sci. Stiller 266 402 1992 10.1016/0039-6028(92)91053-E Intergranular precipitation in Ni-Cr-Fe alloys 

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23. Acta Metall. Kruger 36 12 3163 1988 10.1016/0001-6160(88)90052-1 A quantitative model for the intergranular precipitation of M7X3 and M23X6 in Ni-16Cr-9Fe-C-B 

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24. Coriou 1973 Proceedings of Conference on Fundamental Aspects of Stress Corrosion Cracking and Hydrogen Embrittlement of Iron Base Alloys Historical review of the principal research concerning the phenomena of cracking of nickel base austenitic alloys 

25. EPRI NP-3051 1983 Optimization of Metallurgical Variables to Improve Corrosion Resistance of Inconel Alloy 600 

26. EPRI NP-5987-SP 1988 PWSCC Behavior of Thermally Treated Alloy 600 

27. Corrosion Arioka 62 7 568 2006 10.5006/1.3280670 Influence of carbide precipitation and rolling direction on intergranular stress corrosion cracking of austenitic stainless steels in hydrogenated high-temperature water 

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28. J. Nucl. Mater. Bruemmer 216 348 1994 10.1016/0022-3115(94)90020-5 Microstructural and microchemical mechanisms controlling intergranular stress corrosion cracking in light-water-reactor systems 

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29. Corros. Sci. Huang 75 396 2013 10.1016/j.corsci.2013.06.022 Effects of heat treatment and chromium content on the environmentally assisted cracking behavior of the dissimilar metal welds in simulated BWR coolant environments 

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30. Corros. Sci. Persaud 91 58 2015 10.1016/j.corsci.2014.10.044 The effect of weld chemistry on the oxidation of Alloy 82 dissimilar metal welds 

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31. Corrosion Bruemmer 44 11 782 1988 10.5006/1.3584948 Microstructure and microdeformation effects on IGSCC of alloy 600 steam generator tubing 

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32. Hong 2001 Proc. of the 10th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors Measurement of stress corrosion cracking growth rates in weld alloy 182 in primary water of PWR 

33. Yonezawa 77 1987 Materials for Nuclear Reactor Core Applications 

34. Corros. Sci. Persaud 86 108 2014 10.1016/j.corsci.2014.04.041 Internal oxidation of Alloy 600 exposed to hydrogenated steam and the beneficial effects of thermal treatment 

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35. Gendron 1994 Irreversible Embrittlement of Alloy 600 in Hydrogenated Steam at 400 °C, CORROSION/1994 

36. Corros. Sci. Shen 155 209 2019 10.1016/j.corsci.2019.05.008 The effects of intergranular carbides on the grain boundary oxidation and cracking in a cold-worked Alloy 600 

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37. J. Nucl. Mater. Shen 514 50 2019 10.1016/j.jnucmat.2018.11.020 On the role of intergranular carbides on improving the stress corrosion cracking resistance in a cold-worked alloy 600 

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38. Corros. Sci. Lim 108 125 2016 10.1016/j.corsci.2016.02.040 Intergranular oxidation of Ni-based Alloy 600 in a simulated PWR primary water environment 

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