Microstructure analysis of laser beam weldments performed on neutron-irradiated 304L steel containing 3 and 8 appm helium

M. N. Gussev, W. Zhong, F. A. Garner, P. D. Freyer, J. K. Tatman, J. Werden

Research output: Contribution to journalArticlepeer-review

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Abstract

AISI 304 L austenitic stainless steel is one of the major structural materials used in light water reactors (LWRs). In the future, 304 L components may require repair, and several welding techniques have been proposed as candidates. In this study, laser beam welding using the low-energy contribution approach was performed in ∼2016 on neutron-irradiated AISI 304 L steel with nominal values of 3 and 8 appm helium (He). The goal was to investigate the impact of helium on the irradiated material weldability and evaluate helium-associated damage. The weld and heat-affected zone (HAZ) microstructure was studied using scanning electron microscopy, electron backscatter diffraction, and transmission electron microscopy (TEM). Analysis of the weldment cross-sections did not reveal severe cracking. Still, evidence of incipient helium-associated damage was observed in the HAZ, manifesting as degraded grain boundaries (GBs) “decorated” by pore chains and mostly small (i.e., ≤ 25–30 µm) scattered cracks. The largest observed crack was ∼50 µm in length. Helium-associated damage was localized within ∼200–300 µm of the weld pool boundary, and the fraction of the compromised GBs, as a rule, was below ∼9–11% of the total GB network. TEM analysis showed significant annealing of the radiation-induced defects at distances up to ∼300 µm from the weld pool boundary. Inside the HAZ, the cavities (likely, helium bubbles) tended to form at GBs and inclusions, such as manganese sulfide precipitates in the grain interior. Crystallography analysis of the HAZ damage showed that random high-angle boundaries were most susceptible to helium-associated damage. In contrast, low-angle random boundaries and twin boundaries appeared to be strongly resistant to degradation from the combined effects of helium and welding.

Original languageEnglish
Article number153638
JournalJournal of Nuclear Materials
Volume563
DOIs
StatePublished - May 2022

Funding

The authors would like to thank the National Science User Facilities and especially Dr. Rory Kennedy for providing access to the hex block material from the irradiated material library. The authors would also like to thank Dr. J. Harp (ORNL) and Dr. X. Chen (ORNL) for useful discussions and reviews of the work. The help and support of ORNL's Irradiated Materials Examination and Testing Facility staff (manager: Mark Delph) and the Low-Activation Materials Design and Analysis Laboratory staff (manager: T. Muth) are gratefully acknowledged. The authors also would like to thank L. Varma (ORNL) for help with manuscript preparation. This manuscript has been authored by UT-Battelle LLC under contract DE-AC05–00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan ( http://energy.gov/downloads/doe-public-access-plan ).

FundersFunder number
National Science User Facilities
U.S. Department of Energy
Oak Ridge National Laboratory
UT-BattelleDE-AC05–00OR22725

    Keywords

    • Cracking
    • Grain-boundary degradation
    • Helium-induced embrittlement
    • Irradiated 304 L steel
    • Laser beam welding

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