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K. Colas
K. Colas
Université Paris-Saclay
Ductility
Metallurgy
Yield (engineering)
Zirconium alloy
Cladding (metalworking)
2
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2
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Post irradiation testing capabilities of experimental reactor components at the LECI facility for service life assessment
2017
P. Gavoille
K. Colas
B. Kapusta
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Hydride reorientation and its impact on ambient temperature mechanical properties of high burn-up irradiated and unirradiated recrystallized Zircaloy-2 nuclear fuel cladding with an inner liner
2017
Journal of Nuclear Materials
Quentin Auzoux
P. Bouffioux
Albert J. Machiels
Suresh K. Yagnik
B. Bourdiliau
C. Mallet
N. Mozzani
K. Colas
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