APT characterization of high nickel RPV steels

Journal of Nuclear Materials

Volumn 351, Issue 1-3, 2006, Pages 187-196

  Miller, M K ^a   Sokolov, M A ^a   Nanstad, R K ^a   Russell, K F ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

A0800; P1200; R0200

Indexed keywords

MICROSTRUCTURE; NEUTRON IRRADIATION; NICKEL; PRESSURE VESSELS; TOMOGRAPHY;

A0800; ATOM PROBE TOMOGRAPHY (ATP); P1200; R0200;

STEEL;

EID: 33747150824     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2006.02.013     Document Type: Article

References (31)

1. Kryukov A.M., Nikolaev Y.A., and Nikolaeva A.V. Nucl. Eng. Des. 186 (1998) 353
2. T.J. Williams, P.R. Burtz, C.A. English, P.H.N. de la Cour Ray, in: G.J. Theus, J.R. Weeks (Eds.), 3rd International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors 1987, 1988, p. 121.
3. Odette G.R., and Lucas G.E. In: Steele L.E. (Ed). Irradiation Embrittlement of Reactor Pressure Vessel Steels: An International Review. ASTM STP 909 (1986), ASTM 206
4. Odette G.R., and Lucas G.E. The effect of nickel on irradiation hardening of pressure vessel steels. In: Packan N.H., Stoller R.E., and Kumar A.S. (Eds). Effects of Radiation on Materials: 14th International Symposium. ASTM STP 1046 vol. II (1990), American Society for Testing and Materials, Philadelphia 323
5. G.R. Odette, Radiation induced microstructural evolution in reactor pressure vessel steels, Microstructure of Irradiated Materials, in: MRS Symposium Proceedings, vol. 373, Pittsburgh, PA, 1995, p. 137.
6. Gerard R., et al. In-service embrittlement of the pressure vessel welds at the Doel I and II nuclear power plants. Effects of Radiation on Materials: 17th International Symposium. In: Gelles D.S., Nanstad R.K., Kumar A.S., and Little E.A. (Eds). ASTM STP 1046 vol. II (1996), American Society for Testing and Materials 294
7. G.R. Odette, C.L. Liu, B.D. Wirth, On the composition and structure of nanoprecipitates in irradiated pressure vessel steels, Microstructure Evolution During Irradiation, in: MRS Soc Symposium Proceedings, vol. 439, Pittsburgh, 1997, p. 457.
8. Nikolaev Y.A., et al. Radiation embrittlement and thermal annealing behavior of Cr-Ni-Mo reactor pressure vessel materials. J. Nucl. Mater. 226 (1995) 144
9. Miller M.K. Atom Probe Tomography: Analysis at the Atomic Level (2000), Kluwer Academic/Plenum, New York, NY
10. Miller M.K., Cerezo A., Hetherington M.G., and Smith G.D.W. Atom Probe Field Ion Microscopy (1996), Oxford University, Oxford, UK
11. Miller M.K., Pareige P., and Burke M.G. Mater. Charact. 44 (2000) 235
12. Miller M.K., Hetherington M.G., and Burke M.G. Metall. Trans. 20A (1989) 2651
13. Miller M.K., and Pareige P. In: Lucas G.E., Snead L., Kirk Jr. M.A., and Elliman R.G. (Eds). Proc. MRS 2000 Fall Meeting, Symposium R: Microstructural Processes in Irradiated Materials, Boston, MA, November 27-30, 2000 vol. 650 (2001), Materials Research Society, Pittsburgh, PA R6.1.1
14. Hyde J.M., and English C.A. In: Lucas G.E., Snead L., Kirk Jr. M.A., and Elliman R.G. (Eds). Proc. MRS 2000 Fall Meeting, Symposium R: Microstructural Processes in Irradiated Materials, Boston, MA, November 27-30, 2000 vol. 650 (2001), Materials Research Society, Pittsburgh, PA R6.6.1
15. Miller M.K., Russell K.F., and Pareige P. In: Lucas G.E., Snead L., Kirk Jr. M.A., and Elliman R.G. (Eds). Proc. MRS 2000 Fall Meeting, Symposium R: Microstructural Processes in Irradiated Materials, Boston, MA, November 27-30, 2000 vol. 650 (2001), Materials Research Society, Pittsburgh, PA R3.15.1
16. Miller M.K., Russell K.F., Kocik J., and Keilova E. J. Nucl. Mater. 282 (2000) 83
17. Miller M.K., Russell K.F., Kocik J., and Keilova E. Micron 32 (2001) 749
18. Miller M.K., Babu S.S., Sokolov M.A., Nanstad R.K., and Iskander S.K. Mater. Sci. Eng. A 327 (2002) 76
19. M.K. Miller, M.A. Sokolov, R.K. Nanstad, S.K. Iskander, in: Proc. 10th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Lake Tahoe, NV, August 5-9, 2001, Pub. NACE, 2002.
20. M.G. Burke, R.J. Stofanak, J.M. Hyde, C.A. English, W.L. Server, in: Proc. 10th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Lake Tahoe, NV, August 5-9, 2001, Pub. NACE, 2002.
21. Carter R.G., Soneda N., Dohi K., Hyde J.M., English C.A., and Server W. J. Nucl. Mater. 398 (2001) 211
22. Auger P., Pareige P., Welzel S., and Van Duysen J.C. J. Nucl. Mater. 280 (2000) 331
23. Hyde J.M., Ellis D., English C.A., and Williams T.J. Microstructural evolution in high nickel submerged arc weld. 20th Int. Conf. Effects of Radiation on Materials. In: Rosinski S.T., Grossbeck M.L., Allen T.R., and Kumar A.S. (Eds). ASTM STP 1405 (2001), American Society for Testing and Materials, West Conshohocken, PA 262
24. F.W. Stallmann, J.A. Wang, F.B.K. Kam, PR-EDB: Power Reactor Embrittlement Data Base, Version 2, NUREG/CR-4816, US Nuclear Regulatory Commission, 1994.
25. M.K. Miller, K.F. Russell, Surf. Interface Anal., in press.
26. Nanstad R.K., McCabe D.E., Haggag F.M., Bowman K.O., and Downing D.J. Statistical analyses of fracture toughness results for two irradiated high-copper welds. Effects of Radiation on Materials: 15th International Symposium. In: Stoller R.E., Kumar A.S., and Gelles D.S. (Eds). ASTM STP 1125 (1992), American Society for Testing and Materials, Philadelphia 270
27. McGowan J.J., and Nanstad R.K. A statistical analyses of fracture toughness of irradiated low-alloy steel plate and welds. Influence of Radiation on Material Properties: 13th International Symposium (Part II). In: Garner F.A., Henager Jr. C.H., and Igata N. (Eds). ASTM STP 956 (1987), American Society for Testing and Materials, Philadelphia 569
28. Jc and Charpy impact toughness for reactor pressure vessel steels. Effects of Radiation on Materials: 18th International Symposium. In: Nanstad R.K., Hamilton M.L., Garner F.A., and Kumar A.S. (Eds). ASTM STP 1325 (1999), American Society for Testing and Materials, West Conshohocken, PA 167
29. Regulatory Guide 1.99 Revision 2, Radiation embrittlement of reactor vessel materials, Office of Nuclear Regulatory Research, US Nuclear Regulatory Commission, Washington, DC, May 1988.
30. E.D. Eason, J.E. Wright, G.R. Odette, Improved embrittlement correlations for reactor pressure vessel steels, NUREG/CR-6551, US Nuclear Regulatory Commission, Washington, DC, 1998.
31. ASTM E 900. Guide for predicting radiation-induced transition temperature shift in reactor vessel materials, E706 (IIF). Annual Book of ASTM Standards vol. 12.02 (2002), American Society for Testing and Materials, West Conshohocken, PA