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

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

doi:10.2172/1828253

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

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

Research output: Other contribution › Technical Report

Abstract

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.

Original language	English
Place of Publication	United States
DOIs	https://doi.org/10.2172/1828253
State	Published - 2021

Keywords

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE

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10.2172/1828253

Cite this

@misc{633b543b62a54d2fade9fe303312f8d0,

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

abstract = "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.",

keywords = "22 GENERAL STUDIES OF NUCLEAR REACTORS, 36 MATERIALS SCIENCE",

author = "Byun, \{T. S.\} and Collins, \{David A.\} and \{Le Coq\}, \{Annabelle G.\} and Lach, \{Tim G.\} and Linton, \{Kory D.\} and Gussev, \{Maxim N.\} and Werden, \{Jesse W.\} and Mcalister, \{Michael R.\} and Xiang Chen and Joslin, \{Chase B.\} and Carver, \{J. Keith\} and \{List III\}, \{Fred A.\}",

year = "2021",

doi = "10.2172/1828253",

language = "English",

type = "Other",

}

TY - GEN

T1 - Mechanical Properties of Additively Manufactured 316L Stainless Steel Before and After Neutron Irradiation (FY21)

AU - Byun, T. S.

AU - Collins, David A.

AU - Le Coq, Annabelle G.

AU - Lach, Tim G.

AU - Linton, Kory D.

AU - Gussev, Maxim N.

AU - Werden, Jesse W.

AU - Mcalister, Michael R.

AU - Chen, Xiang

AU - Joslin, Chase B.

AU - Carver, J. Keith

AU - List III, Fred A.

PY - 2021

Y1 - 2021

N2 - 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.

AB - 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.

KW - 22 GENERAL STUDIES OF NUCLEAR REACTORS

KW - 36 MATERIALS SCIENCE

U2 - 10.2172/1828253

DO - 10.2172/1828253

M3 - Technical Report

CY - United States

ER -

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

Abstract

Keywords

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