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M.R. Finlay
M.R. Finlay
Australian Nuclear Science and Technology Organisation
Research reactor
Radiochemistry
Irradiation
Chemistry
Fabrication
5
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93
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Fabrication and testing of U–7Mo monolithic plate fuel with Zircaloy cladding
2016
Journal of Nuclear Materials
E.E. Pasqualini
A.B. Robinson
Douglas L. Porter
D. M. Wachs
M.R. Finlay
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Interaction layer growth correlations for (U-Mo)/A1 and Si-added (U-Mo)/A1 dispersion fuels.
2006
Yeon So Kim
Ho Jin Ryu
G.L. Hofman
S.L. Hayes
M.R. Finlay
D. M. Wachs
G. S. Chang
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Session 2 Fuel development, qualification, fabrication and licensing
2005
J. L. Snelgrove
P. Lemoine
L. Alvarez
F. Huet
C. Jarousse
C. Curtis
S.L. Hayes
D. M. Wachs
M. K. Meyer
G.L. Hofman
M.R. Finlay
A. Vatulin
A. Morozov
V. Suprun
I.V. Dobrikova
V. Marelle
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Irradiation behaviour of uranium silicide compounds
2004
Journal of Nuclear Materials
M.R. Finlay
G.L. Hofman
J. L. Snelgrove
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Recent observations at the post-irradiation examination of low-enriched U-Mo miniplates irradiated to high burn-up
2003
G.L. Hofman
Yeon So Kim
M.R. Finlay
J. L. Snelgrove
S.L. Hayes
M. K. Meyer
C. R. Clark
F. Huet
Commissariat l'Energie Atomique Cadarache
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Citations (20)
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