Hostname: page-component-8448b6f56d-tj2md Total loading time: 0 Render date: 2024-04-25T02:15:04.609Z Has data issue: false hasContentIssue false

Examination of Neutron-Irradiated Pressure-Vessel Steel Using Positron Annihilation Lifetime Spectrosopy

Published online by Cambridge University Press:  15 February 2011

Stephen E. Cumblidge
Affiliation:
Department of Mechanical and Nuclear Engineering, The Pennsylvania State University, University Park, PA, 16802, USA
Arthur T. Motta
Affiliation:
Department of Mechanical and Nuclear Engineering, The Pennsylvania State University, University Park, PA, 16802, USA
Gary L. Catchen
Affiliation:
Department of Mechanical and Nuclear Engineering, The Pennsylvania State University, University Park, PA, 16802, USA
Get access

Abstract

On a variety of pressure-vessel (PV) steels, we have observed changes in the average positron lifetime with increasing (near end-of-life) neutron fluences. Samples were irradiated at reactor-temperature and subjected to post-irradiation annealing, and they were examined using positron annihilation lifetime spectroscopy (PALS). The measured average positron lifetimes in high-temperature (2900 C-300° C) irradiated PV steels decrease with increasing neutron damage up to fluences of 8.5×1018 cm−2 and increase again at higher fluences. Annealing of high-fluence, 300° C irradiated ASTM A508 PV steel samples produces an initial decrease in average positron lifetimes with increasing annealing temperatures of up to 400° C, followed by an increase in average positron lifetime with higher annealing temperatures, when samples were annealed in successive 24-hour steps. A sample of weld steel, irradiated to 2.2×1019 cm−2 at 290° C, shows similar behavior in which the minimum lifetime occurs at ≈ 450° C. These trends are similar to those seen in previous studies performed on VVER and other ferritic steels.

Type
Research Article
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] Brauer, G., Liszkay, L., Molnar, B., Krause, R., Nucl.Eng. and Design, 127 (1991), 4768.Google Scholar
[2] Lopes-Gil, C., Lima, A. P. De, Campos, N. Ayres De, V, J., Fernandes, G. Koegel, Sperr, P., Triftshaeuser, W., Pachur, D., J. Nucl. Mater. 161 (1989) 112.Google Scholar
[3] Pareja, R., Diego, N. de, Cruz, R. de la, Rio, J. del, Nuclear Technology, 104 (1993) 5263.Google Scholar
[4] Groβe, M., Eichhorn, F., Böhmert, J., Brauer, G., Haubold, H-G., and Goerigk, G., Nuclear Instruments and Methods in Physics Research B 97 (1995) 487490.Google Scholar
[5] Brauer, G., Matz, W., and Fetzer, Cs., Hyperfine Interactions 56 (1990) 15631568.Google Scholar
[6] Cumblidge, S.E., Motta, A.T., and Catchen, G.L., Materials Research Society Symposium Proceedings vol. 439 (1997), 483488 Google Scholar
[7] Kirkegaard, P., Eldrup, M., Mogensen, O. E., and Pedersen, N. J., Comput. Phys. Commun. 23 (1981) 307.Google Scholar
[8] Pachur, D., Nuclear Technology, 59 (1982) 463.Google Scholar
[9] Stoller, R.E., Effects of Radiation on Materials: 17th International Symposium, ASTM STP 1270, Gelles, D.S., Nanstad, R.K., Kumar, A.S., Little, E.A., eds. (1996) 2558.Google Scholar
[10] Brauer, G., Puska, M.J., Sob, M., and Korhhonen, T., Nucl.Eng.Des. 158 (1995) 149156.Google Scholar
[11] Odette, G.R., Scripta Met. 17 (1983) 11831188.Google Scholar
[12] Seitzman, W., Berggren, R.G., and Jones, T.N. Jr., ORNL report no. TM-9491, April 1985.Google Scholar
[13] Nanstad, R.K., Haggag, F.M., McCabe, D.E., Iskander, S.K., Bowman, K.O., and Menke, B.H., ORNL report no. TM-12156, vol.1, October, 1992.Google Scholar
[14] Nanstad, R.K., McCabe, D.E., Swain, R.L., and Miller, M., ORNL report no.6740, December 1992.Google Scholar