Abstract
DURING development work on fuel elements for fast reactor applications, electron microscope examination by the thin foil technique has been carried out on samples of stainless steel irradiated in the Dounreay Fast Reactor, either in the form of cladding on experimental fuel elements or as specimens intended for mechanical property tests. The steel had a composition falling within the American Iron and Steel Institute type 316 specification as shown by the analysis given in Table 1.
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References
Rowcliffe, A. F., et al., UKAEA, TRG Report 1283 (C) (1966).
Fraser, A. S., Birss, I. R., and Cawthorne, C., Nature, 211, 291 (1966).
Birss, I. R., Nuclear Eng., 10, 465 (1965).
Barnes, R. S., and Mazey, D. J., Proc. Roy. Soc., A, 275, 47 (1963).
Brown, L. M., and Mazey, D. J., Phil Mag., 10, 1081 (1964).
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CAWTHORNE, C., FULTON, E. Voids in Irradiated Stainless Steel. Nature 216, 575–576 (1967). https://doi.org/10.1038/216575a0
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DOI: https://doi.org/10.1038/216575a0
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