Design and screening of nanoprecipitates-strengthened advanced ferritic alloys

Lizhen Tan, Ying Yang, Tianyi Chen, K. Sridharan, Li He

Research output: Other contributionTechnical Report

Abstract

Advanced nuclear reactors as well as the life extension of light water reactors require advanced alloys capable of satisfactory operation up to neutron damage levels approaching 200 displacements per atom (dpa). Extensive studies, including fundamental theories, have demonstrated the superior resistance to radiation-induced swelling in ferritic steels, primarily inherited from their body-centered cubic (bcc) structure. This study aims at developing nanoprecipitates strengthened advanced ferritic alloys for advanced nuclear reactor applications. To be more specific, this study aims at enhancing the amorphization ability of some precipitates, such as Laves phase and other types of intermetallic phases, through smart alloying strategy, and thereby promote the crystalline®amorphous transformation of these precipitates under irradiation.
Original languageEnglish
Place of PublicationUnited States
DOIs
StatePublished - 2016

Keywords

  • 36 MATERIALS SCIENCE
  • FERRITIC STEELS
  • BCC LATTICES
  • WATER MODERATED REACTORS
  • ATOMIC DISPLACEMENTS
  • WATER COOLED REACTORS
  • LAVES PHASES

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