Impact of Low-Temperature Neutron Irradiation on Tensile Behavior of Base Metal and Electron-Beam Welded 316L Stainless Steel

Chinthaka M. Silva, Keith J. Leonard, Lauren M. Garrison, Chris D. Bryan, Kiel S. Holliday

Research output: Contribution to journalArticlepeer-review

1 Scopus citations

Abstract

A study of 316L type stainless steel in its base metal and electron-beam (e-beam) welded conditions was performed to observe the effects of low-temperature (60 °C to 100 °C) neutron irradiation on the tensile behavior of the samples. Fractography was used in understanding the tensile-tested fracture surfaces of the 316L samples in these different forms with the characterization of the both base metal and welded samples using electron microscopy. Irradiation of the tensile specimens made free of defects of cutting and mechanical polishing showed a reduction in their tensile ductility with increased radiation-induced hardening up to 1.40 × 1019 n/cm2 (E > 0.1 MeV) fluence that corresponds to 1.1× 10−2 dpa, even at the low irradiation temperatures. These low-temperature neutron irradiated base metal and e-beam welded 316L specimens also consisted of closely similar fracture surfaces characteristic of ductile rupture.

Original languageEnglish
Pages (from-to)3615-3626
Number of pages12
JournalMetallurgical and Materials Transactions A: Physical Metallurgy and Materials Science
Volume53
Issue number10
DOIs
StatePublished - Oct 2022

Funding

Funding for this research work was provided by the US Department of Energy’s National Nuclear Security Administration (DOE/NNSA), Office of Material Management and Minimization’s Molybdenum-99 Program. The authors would also like to thank their coworkers at ORNL for their support in this research work: Tom Geer, Christopher Stevens, Michael McAlister, Maxim Gussev, Pat Bishop, and Joel McDuffee. This work was also performed under the auspices of the U.S. Department of Energy (DOE) by Lawrence Livermore National Laboratory (LLNL) under Contract No. DE-AC52-07NA27344. Funding for this research work was provided by the US Department of Energy’s National Nuclear Security Administration (DOE/NNSA), Office of Material Management and Minimization’s Molybdenum-99 Program. The authors would also like to thank their coworkers at ORNL for their support in this research work: Tom Geer, Christopher Stevens, Michael McAlister, Maxim Gussev, Pat Bishop, and Joel McDuffee. This work was also performed under the auspices of the U.S. Department of Energy (DOE) by Lawrence Livermore National Laboratory (LLNL) under Contract No. DE-AC52-07NA27344. On behalf of all authors, the corresponding author states that there is no conflict of interest.

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