Hostname: page-component-848d4c4894-4rdrl Total loading time: 0 Render date: 2024-06-19T01:52:43.581Z Has data issue: false hasContentIssue false
  • English
  • Français

Effects of Pre-Existing Thermal Sensitization on the Radiation Induced Sensitization in Type 304 Stainless Steels

Published online by Cambridge University Press:  15 February 2011

L.H. Wang ,
C.H. Tsai ,
J.J. Kai  and
T.S. Duh
L.H. Wang
Affiliation:
Materials Research Labs./Industrial Technology Research Institute, Hsinchu, Taiwan
C.H. Tsai
Affiliation:
National Tsing-Hua University, Hsinchu, Taiwan
J.J. Kai
Affiliation:
National Tsing-Hua University, Hsinchu, Taiwan
T.S. Duh
Affiliation:
National Tsing-Hua University, Hsinchu, Taiwan
Get access

Abstract

I is generally recognized that radiation induced sensitization plays an important role in initiating irradiation assisted stress corrosion cracking (IASCC) of austenitic stainless steels in reactor core internal of light water reactor. However, the synergism between radiation sensitization and prior thermal sensitization is unclear. This situation is likely to occur in most welded core internal structures subjected to neutron irradiation. In this study, the effect of prior thermal treatment on radiation sensitization were investigated on proton irradiated Type 304 stainless steel (SS) of initially as-received (AR) and thermal-sensitized (SEN) conditions. The Cr depletion profiles were measured by field emission gun transmission electron microscopy/ energy dispersive spectroscopy (FEGTEM / EDS), and were calculated by a radiation induced segregation (RIS) model.

The different initial conditions were input in the RIS model calculations. For the asreceived condition, the initial Cr profile was modeled by a uniform concentration distribution. For the initially thermal-sensitized condition, the wider Cr depletion profile measured by FEGTEM / EDS was input as the initial condition. The results showed that radiation sensitization is characterized by a very narrow Cr depleted zone. The Cr content at grain boundary tends to be lower as radiation dose increases. Comparing with the non-sensitized (asreceived) specimens with the same dosage, the grain boundary Cr content without prior sensitization is higher than that with sensitization pre-treatment. The deeper grain boundary Cr concentration of irradiated thermally sensitized sample is induced not only from proton irradiation effect, but also resulted from the pre-existing Cr depletion.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 540: Symposium N / Microstructural Processes in Irradiated Materials , 1998 , 489
Copyright
Copyright © Materials Research Society 1999

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

1. Stawstrom, C. and Hillert, M., J. Iron Steel Inst., 77, 1511(1969)Google Scholar
2. Tedmon, C.S. Jr., Vermilyea, D.A. and Rosolowski, H.H., J. Electrochem. Soc., 2, 192(1971)Google Scholar
3. Bruemmer, S.M., Corroion/89, edited by NACE, , (New Orleans, LA, 1989) paper number 561 Google Scholar
4. Grujicic, M. and Tangrila, S., Materials Science and Engineering, A142, 255(1991)Google Scholar
5. Perks, J.M., Marwick, A.D. and English, C.A., Proceedings of Symposium on Radiation Induced Sensitization of Stainless Steels, edited by Norris, D.I.R., (CEGB, Berkeley Nuclear Laboratories, Berkeley, September 1986) p. 15 Google Scholar
6. Simonen, E.P., Charlot, L.A. and Bruemmer, S.M., Corrosion/91, edited by NACE, , ( Ohio, 1991)paper number 39 Google Scholar
7. Was, G. S., Allen, T., J. Nuclear Mater, 205, 332(1993)Google Scholar
8. Simonen, E.P. and Bruemmer, S.M., Proceedings of the 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, edited by ANS, (Amelia Island, Florida, 1997) p. 751 Google Scholar
9. Simonen, E.P. and Bruemmer, S.M., Corrosion/98, edited by NACE, (San Diego, CA, 1998) paper number 139 Google Scholar
10. Biersack, J. P., Haggmark, L. G., Nuclear Instruments and Methods, 174, 257(1980)Google Scholar
11. Clarke, W. L., NUREG-0251-1, August 1976 ; NUREG/CR-1095, February 1981, US Nuclear Regulatory Commission, Washington, DCGoogle Scholar
12. Kai, J. J. et al. , Proceedings of 8rh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, edited by ANS, ( Amelia Island, Florida, 1997) p.766 Google Scholar
3. Okada, O., Nakata, K., Kasahara, S. and Aoyama, T., Proceedings of the 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, edited by ANS, (Amelia Island, Florida, 1997) p.743 Google Scholar
14. Bruemmer, S. M. et al. , Corrosion, 44(6), p. 328( 1988)Google Scholar