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Comparison Between 590 Mev Proton Irradiation and Neutron Irradiation on the F82H Ferritic/Martensitic Steel

Published online by Cambridge University Press:  15 February 2011

R. Schäublin
Affiliation:
CRPP, Fusion technology, Materials Group, Ecole Polytechnique Fédérale de Lausanne, CH- 5232 Villigen – PSI, Switzerland
M. Victoria
Affiliation:
CRPP, Fusion technology, Materials Group, Ecole Polytechnique Fédérale de Lausanne, CH- 5232 Villigen – PSI, Switzerland
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Abstract

The microstructure of the low activation F82H ferritic/martensitic steel, which is a candidate for future fusion reactor first wall, has been studied in order to determine the differences between 590 MeV proton irradiations and fission neutron irradiations. A range of doses and temperatures are investigated. The present work focuses on the microstructure of irradiation induced defect clusters for cases of proton irradiations to doses up to 1.7 dpa, and for neutron irradiation to a single dose of 2.5 dpa. The irradiation temperatures were 40°C and 250°C in the case of the proton irradiation and 250°C in the case of the neutron irradiation. In the case of the proton irradiation no defects are observed in the transmission electron microscope in the case of the 0.45 dpa dose, while they start to be clearly visible for doses higher than about 1.0 dpa. In the case of the neutron irradiation a high density of defects and small loops is evidenced. These preliminary results are presented here.

Type
Research Article
Copyright
Copyright © Materials Research Society 1999

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References

[1] Klueh, R.L., Alexander, D.J., Journal of Nuclear Materials, p. 187, 187 (1992).Google Scholar
[2] Kimura, A., Charlot, L.A., Gelles, D.S., Jones, R.H., Journal of Nuclear Materials, p. 212215, 725 (1994).Google Scholar
[3] Watanabe, S., Sakaguchi, N., Kurome, K., Nakamura, M., Takahashi, H., Journal of Nuclear Materials, p. 251, 240 (1997).Google Scholar
[4] Schäublin, R., Spätig, P., Victoria, M., Journal of Nuclear Materials, p. 1350, 258–263 (1998).Google Scholar
[5] Kasahara, S., Nakata, K., Takahashi, H., Journal of Nuclear Materials, p. 194, 239 (1996).Google Scholar
[6] Liu, C., Abiko, K., Tanino, M., Materials Science and Engineering, p. 363, A176 (1994).Google Scholar
[7] Little, E. A., Stow, D.A., Journal of Nuclear Materials, p. 25, 87 (1979).Google Scholar
[8] Gelles, D.S., Journal of Nuclear Materials, p. 515, 108 & 109 (1982).Google Scholar
[9] Katoh, Y., Kohyama, A., Gelles, D.S., Journal of Nuclear Materials, p. 154, 225 (1995).Google Scholar
[10] Bae, K.K., Ehrlich, K., Möslang, A., Journal of Nuclear Materials, p. 905, 191–194 (1992).Google Scholar
[11] Shiba, K., Suzuki, M., Hishinuma, A. and Pawel, J.E. in Effects of Radiation on Materials: Tenth conference, edited by Gelles, D.S., Nanstad, R.K., Kumar, A.S. and Little, E.A. (ASTM STP 1270, ASTM 1996) p. 753.Google Scholar
[12] Green, S.L., Journal of Nuclear Materials, p. 30, 126 (1984).Google Scholar
[13] Little, E.A., Journal of Nuclear Materials, p. 11, 87 (1995).Google Scholar
[14] Bullough, R., Wood, M.H. and Little, E.A. in Effects of Radiation on Materials: 10th conference, edited by Kramer, D., Brager, H.R. and Perrin, J.S. (ASTM STP 725, ASTM 1981) p. 593.Google Scholar
[15] Tamura, M., Hayakawa, H., Tanimura, M., Hishinuma, A., Kondo, T., Journal of Nuclear Materials, p. 1067, 141–143 (1986).Google Scholar
[16] Marmy, P., Daum, M., Gavillet, D., Green, S., Green, W.V., Hegedus, F., Proennecke, S., Rohrer, U., Stiefel, U. and Victoria, M., NIM B 37 (1990).Google Scholar
[17] Spätig, P., Schäublin, R., Gyger, S., Victoria, M., Journal of Nuclear Materials, p. 1345, 258–263 (1998).Google Scholar