Damage Evolution in Thin Foils of UHP-Fe and FeCr Alloys at High Doses
Damage
Evolution in Thin Foils of UHP-Fe and FeCr Alloys at High Doses
Scientific
Achievement
We have carried out an investigation of damage
development in UHP Fe and
Fe-8%Cr at higher doses up to 2 x 1019 ions m-2
(~13
dpa). In thin-foil
irradiations with 150
keV Fe+ ions at temperatures from room
temperature (RT) to 500oC
significant complex microstructures started to develop in thicker
regions of
the foils at doses greater than about 2 x 1018
ions m-2,
seeming to involve cooperative interaction, alignment and coalescence
of
smaller loops. First
strings of loops
all with the same ˝<111> Burgers vectors formed. In UHP Fe irradiated at 300oC
the
damage then developed into colonies of resolvable interstitial loops
with
˝<111> Burgers vectors.
By a dose
of 2 x 1019 ions m-2,
large (several hundred nanometre)
finger-shaped loops with large shear components had developed by the
growth and
subsequent coalescence of smaller loops.
Similar but not identical damage structures developed in
UHP Fe
irradiated at RT and in Fe-8%Cr irradiated at both RT and 300oC. At 500oC,
square-shaped
interstitial loops with b =
<100> nucleated and grew to large sizes.
Damage structures in FeCr were similar but on a finer
scale. Small voids
were found at both 300oC and 500oC. Evidently we unveiled a
truth that there is a
transition from 1/2<111> type predomination into
<100>
predomination at certain temperature between 450oC
and 500oC.
Significance
The very complex and beautiful microstructures
which develop at high
doses were quite unexpected, and could not have been understood without
these in situ experiments. Perhaps
the most
significant result here is the transition in loop types from ˝
<111> at
lower temperatures to <100> at higher temperatures. This transition is the
subject of further
experiments. A
similar result has now
been found in ex situ irradiations,
and it may well have important consequences on the use of ferritic
alloys at
high temperatures in future fusion and Generation IV fission reactors. Some of this work has been
published in Phil.
Mag. 88, 2851-2880 (2008). A
second paper is in press in J.Nuclear Materials,
and further papers are
in preparation.
Performers
M.
Hernández-Mayoral (CIEMAT); Z.
Yao, M. L. Jenkins (U. Oxford); M. A. Kirk (Argonne-MSD)

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