Mechanical Properties of Additively Manufactured 316L Stainless Steel Before and After Neutron Irradiation (FY21)

Technical Report · Sun Aug 01 00:00:00 EDT 2021

DOI:https://doi.org/10.2172/1828253· OSTI ID:1828253

Byun, T. S.  ^[1]; Collins, David A. ^[1]; Le Coq, Annabelle G. ^[1]; Lach, Tim G.  ^[1]; Linton, Kory D. ^[1]; Gussev, Maxim N.  ^[1]; Werden, Jesse W. ^[1]; Mcalister, Michael R. ^[1]; Chen, Xiang  ^[1]; Joslin, Chase B. ^[1]; Carver, J. Keith  ^[1]; List, III, Fred A.  ^[1]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

This report presents the materials property data of additively manufactured (AM) 316L stainless steel (SS) accumulated for the assessment of core materials in the Transformational Challenge Reactor (TCR) program. The TCR manufacturing approach includes using the laser powder bed fusion (LPBF) method for metallic (316L and Inconel 718) components. To assess the mechanical performance of printed components in reactor-relevant conditions and build a property database for the AM materials, mechanical tests and evaluations were performed before and after neutron irradiation. Miniature tensile specimens were irradiated in the High Flux Isotope Reactor to 0.2, 2, 8, and 10 dpa at target temperatures of 300 and 600°C. Postirradiation evaluation for the 0.2 and 2 dpa specimens was performed during FY20 and FY21, and the results are presented and discussed in this document.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1828253
• Report Number(s): ORNL/TM-2021/2121; TRN: US2301970
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE