Abstract
In this paper, 316L stainless steel (316L SS) straight walls, curved walls, and vessels were printed by wire arc additive manufacturing (WAAM) using the 316L SS welding wire to demonstrate the feasibility of spent nuclear fuel (SNF) canister fabrication using this advanced manufacturing technique. Helium leak tests with a leak-tight criteria of 1 × 10-7 ref-cc/s were performed on the printed vessels with various wall thicknesses. Testing pressures ranged from 0.345 MPa (50 psi) to 1.724 MPa (250 psi). Printed wall microstructures were characterized using optical microscopy (OM) and scanning electron microscopy (SEM). Tensile specimens were machined from the printed walls along length, height, and thickness directions and were tested at different temperature conditions, including room temperature and at 80, 150 and 250°C. Results show that all five WAAM-printed canisters with different thickness passed the American National Standards Institute (ANSI) N14.5 helium leak tight criteria for radioactive materials containers. Dispersed micrometer-level size inclusions/voids were observed at the printed wall cross sections, dendritic microstructures were found with grain size variation through the welding torch shifting direction, and very small amounts of δ-ferrite and σ-phase were also observed in those cross sections. The printed walls were ductile, all tensile specimens broke with large plastic deformation/elongation and without brittle failure, and the yield and tensile strengths of the printed specimens at room temperature and 80°C were greater than the minimum values for 316L SS pressure vessels and for general applications at room temperature as required by the ASTM standard, respectively.
| Original language | English |
|---|---|
| Title of host publication | Proceedings of the International High-Level Radioactive Waste Management Conference, IHLRWM 2022, Embedded with the 2022 ANS Winter Meeting |
| Publisher | American Nuclear Society |
| Pages | 43-52 |
| Number of pages | 10 |
| ISBN (Electronic) | 9780894487897 |
| DOIs | |
| State | Published - 2022 |
| Event | 2022 International High-Level Radioactive Waste Management Conference, IHLRWM 2022, Embedded with the 2022 ANS Winter Meeting - Phoenix, United States Duration: Nov 13 2022 → Nov 17 2022 |
Publication series
| Name | Proceedings of the International High-Level Radioactive Waste Management Conference, IHLRWM 2022, Embedded with the 2022 ANS Winter Meeting |
|---|
Conference
| Conference | 2022 International High-Level Radioactive Waste Management Conference, IHLRWM 2022, Embedded with the 2022 ANS Winter Meeting |
|---|---|
| Country/Territory | United States |
| City | Phoenix |
| Period | 11/13/22 → 11/17/22 |
Funding
The work performed in this paper was funded by the US Department of Energy (DOE) Office of Nuclear Energy (NE) Office of Spent Fuel and Waste Disposition (SFWD) Integrated Waste Management (IWM), within work package SF-210OR2020091dd,izatio“StannanIndatiotegn.” The authors gratefully acknowledge the specimens cutting, preparation, machining coordination, and testing by Alan Fredrick, Doug Kyle, Sam Williams, Ian Stinson, viraonoCx,TVriD oon,OCLoerc dDell,Ta , and pressure and leak testing by Eric Vidal. The authors acknowledge Xiang Chen, Yukinori Yamamoto, and Abiodun Adeniyi for reviewing this report, as well as input from technical discussions with Roger Miller. 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- 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). The work performed in this paper was funded by the US Department of Energy (DOE) Office of Nuclear Energy (NE) Office of Spent Fuel and Waste Disposition (SFWD) Integrated Waste Management (IWM), within work package SF-21OR02020109, “Standardization and Integration.” The authors gratefully acknowledge the specimens cutting, preparation, machining coordination, and testing by Alan Fredrick, Doug Kyle, Sam Williams, Ian Stinson, Victoria Cox, Dixon Travis, Colton O'Dell, and Tracie Lowe, and pressure and leak testing by Eric Vidal. The authors acknowledge Xiang Chen, Yukinori Yamamoto, and Abiodun Adeniyi for reviewing this report, as well as input from technical discussions with Roger Miller.
