Design and screening of nanoprecipitates-strengthened advanced ferritic alloys

Technical Report · Fri Dec 30 00:00:00 EST 2016

DOI:https://doi.org/10.2172/1341567· OSTI ID:1341567

Tan, Lizhen ^[1]; Yang, Ying ^[1]; Chen, Tianyi ^[1]; Sridharan, K. ^[2]; He, Li ^[2]

---

1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
2. Univ. of Wisconsin, Madison, WI (United States)

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.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1341567
• Report Number(s): ORNL/TM-2016/726; TRN: US1701845
• Country of Publication: United States
• Language: English

Related Subjects

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