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Performance Of Laser Additively Manufactured Alloys In (Light Water) Reactor Environments

Nuclear power has been the largest source of carbon-free power in the U.S. (and much of the developed world) for almost a half century. As such, in the U.S. today, nuclear power plants of the Light Water Reactor (LWR) design generate 20% of all electricity, comprising over half of carbon-free electricity generation. In order to meet the short-term 2030 greenhouse gas emission reduction target, the existing nuclear fleet will play an important role, while the development and deployment of advanced reactors such as the small modular reactors (SMR) of the LWR design can be accelerated.

Product Number: ED22-17282-SG
Author: Bogdan Alexandreanu, Xuan Zhang, Yiren Chen
Publication Date: 2022
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Metal additive manufacturing (AM) or 3D printing has the potential to transform the nuclear industry by producing high quality components faster and cheaper, thus enhancing the operating performance of current plants and advanced reactors. However, a lack of clarity on the qualification, standards and regulatory pathways for AM fabricated nuclear components are potential obstacles to their use. Nevertheless, the US Nuclear Regulatory Commission (NRC) staff has indicated a performance-based approach rather than an approval of specific AM methods is a more likely certification process for AM components. This paper describes a case study involving one class of austenitic alloy used extensively in the nuclear industry –Type 316L SS – and covers several areas ranging from AM fabrication to characterization and materials testing in the LWR environment. The AM alloy’s response to mechanical testing is correlated with its microstructural features, and, overall, the performance of the AM alloy in the as-built condition was found to be similar to that “traditionally” produced alloys that are currently in use, suggesting that the use of AM for fabricating pressure boundary components for LWRs is plausible.


Metal additive manufacturing (AM) or 3D printing has the potential to transform the nuclear industry by producing high quality components faster and cheaper, thus enhancing the operating performance of current plants and advanced reactors. However, a lack of clarity on the qualification, standards and regulatory pathways for AM fabricated nuclear components are potential obstacles to their use. Nevertheless, the US Nuclear Regulatory Commission (NRC) staff has indicated a performance-based approach rather than an approval of specific AM methods is a more likely certification process for AM components. This paper describes a case study involving one class of austenitic alloy used extensively in the nuclear industry –Type 316L SS – and covers several areas ranging from AM fabrication to characterization and materials testing in the LWR environment. The AM alloy’s response to mechanical testing is correlated with its microstructural features, and, overall, the performance of the AM alloy in the as-built condition was found to be similar to that “traditionally” produced alloys that are currently in use, suggesting that the use of AM for fabricating pressure boundary components for LWRs is plausible.