Memorias de investigación
Ponencias en congresos:
Interstitial defects stability in FeCr alloys vs Cr concentration
Año:2011
Áreas de investigación
  • Ingenierías
Datos
Descripción
Finding adequate materials to withstand the demanding conditions in the future fusion and fission reactors is a real challenge in the development of these technologies. Structural materials need to sustain high irradiation doses and temperatures that will change the microstructure over time. A better understanding of the changes produced by the irradiation will allow for a better choice of materials, ensuring a safer and reliable future power plants. High-Cr ferritic/martensitic steels head the list of structural materials due to their high resistance to swelling and corrosion. However, it is well known that these alloys present a problem of embrittlement, which could be caused by the presence of defects created by irradiation as these defects act as obstacles for dislocation motion. Therefore, the mechanical response of these materials will depend on the type of defects created during irradiation. In this work, we address a study of the effect Cr concentration has on single interstitial defect formation energies in FeCr alloys.
Internacional
Si
Nombre congreso
15th International Conference on Fusion Reactor Materials. (ICFRM2011) Charleston, Carolina del Sur (EEUU) (16-22 October, 2011)
Tipo de participación
960
Lugar del congreso
Revisores
Si
ISBN o ISSN
0000-0000
DOI
Fecha inicio congreso
16/10/2011
Fecha fin congreso
22/10/2011
Desde la página
0
Hasta la página
1
Título de las actas
Proceedings of the Conference
Esta actividad pertenece a memorias de investigación
Participantes
Grupos de investigación, Departamentos, Centros e Institutos de I+D+i relacionados
  • Creador: Grupo de Investigación: Fusión Nuclear Inercial y Tecnología de fusión
  • Centro o Instituto I+D+i: Instituto de Fusión Nuclear
  • Departamento: Ingeniería Nuclear