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Carbon-vacancy complexes as traps for self-interstitial clusters in Fe-C alloys

Autor
Anento, N.; Serra, A.
Tipus d'activitat
Article en revista
Revista
Journal of nuclear materials
Data de publicació
2013-09-01
Volum
440
Número
1-3
Pàgina inicial
236
Pàgina final
242
DOI
https://doi.org/10.1016/j.jnucmat.2013.04.087 Obrir en finestra nova
Projecte finançador
Evolución nano y micro-estructural en metales sometidos a deformación pástica y daño por radiación.
PREDICTION OF THE EFFECTS OF RADIATION FOR REACTOR PRESSURE VESSEL AND IN-CORE MATERIALS USING MULTI-SCALE MODELLING - 60 YEARS FORE
Resum
Self-interstitial loops in irradiated Fe–C alloys are formed by the growth of small self-interstitial atom clusters created directly in cascades. For these clusters to grow up to visible sizes they should be stopped by traps otherwise they would disappear in sinks due to their high one dimensional mobility. The well-known affinity of carbon with vacancies in a-Fe leads to the formation of carbon–vacancy (C–V) complexes that are potential candidates as traps for SIA loops. Applying molecula...
Paraules clau
Dany per radiació, Dinàmica Molecular, aglomerats de defectes, defectes puntuals, difusió.
Grup de recerca
SC-SIMBIO - Sistemes complexos. Simulació discreta de materials i de sistemes biològics

Participants