Performance of a ferritic/martensitic steel for nuclear reactor applications fabricated using additive manufacturing

Niyanth Sridharan, Maxim N. Gussev, Kevin G. Field

Research output: Contribution to journalArticlepeer-review

46 Scopus citations

Abstract

Ferritic/martensitic (FM) steels are being targeted for use in a range of advanced reactor concepts as cladding and structural components. FM steels for nuclear reactor applications have historically been produced using traditional methods (e.g., casting and forging), but recently, additive manufacturing processes have become of interest for making FM-based components. Here, the laser-blown-powder additive manufacturing process was used to fabricate an FM steel, HT9, followed by microstructural and mechanical performance evaluations to determine the viability of future use of additive manufacturing for FM-based component fabrication. Results showed that the as-built condition formed a layered structure with alternating layers of δ-ferrite and martensite, which resulted in anisotropic engineering and true-stress, true-strain mechanical performance. Post-build normalizing and tempering treatments alerted the prior austenite grain size and precipitate distributions, and drove the mechanical performance to near-isotropic properties that mimic wrought-processed properties. The resulting microstructures in all conditions were rationalized in the context of multi-pass welding and the synergies are discussed.

Original languageEnglish
Pages (from-to)45-55
Number of pages11
JournalJournal of Nuclear Materials
Volume521
DOIs
StatePublished - Aug 1 2019

Funding

The work presented in this paper was supported by the Advanced Fuels Campaign of the Nuclear Technology Research and Development program in the Office of Nuclear Energy, U.S. Department of Energy. The FEI (now Thermo Fisher Scientific) Talos F200X instrument used in this work was provided by the Department of Energy, Office of Nuclear Energy, Fuel Cycle R&D Program and the Nuclear Science User Facilities. The authors would like to thank B. H. Jordan for his support during the AM specimen preparation and D. W. Coffey for her careful preparation of the TEM specimens used for this study. The work presented in this paper was supported by the Advanced Fuels Campaign of the Nuclear Technology Research and Development program in the Office of Nuclear Energy, U.S. Department of Energy . The FEI (now Thermo Fisher Scientific) Talos F200X instrument used in this work was provided by the Department of Energy, Office of Nuclear Energy, Fuel Cycle R&D Program and the Nuclear Science User Facilities . The authors would like to thank B. H. Jordan for his support during the AM specimen preparation and D. W. Coffey for her careful preparation of the TEM specimens used for this study.

FundersFunder number
U.S. Department of Energy
Office of Nuclear Energy
Forschungskreis der Ernährungsindustrie

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