Abstract
To develop advanced nuclear fuel claddings, two oxide dispersion strengthened (ODS) alloys were designed, manufactured, and evaluated. First, 12 %Cr alloy, is an ODS-version of ferritic steel, and second, 10 %Cr-6 %Al alloy, is a high-strength version of accident tolerant iron-chrome-aluminum alloy. Their properties and performance were compared with “classical” ODS material, 14 %Cr alloy 14WYT. Thin-walled (∼500 µm wall thickness) tubes were manufactured successfully using the pilgering technique. For all alloys, axial tensile specimens exhibited high tensile strength (>1 GPa) and reasonable plastic strains (10–17%). Ring tensile specimens, conversely, showed limited ductility (∼1%) with similar strengths to those measured in the axial orientation. The grain size, precipitate dispersion characteristics, and dislocation densities were then used to estimate yield strengths that were compared against room temperature axial and ring-pull tensile test data. The strengthening models showed mixed agreement with experimentally measured values due to the highly anisotropic microstructures of all three ODS tubes. These results illustrate the need for future model optimization to accommodate non-isotropic microstructures associated with components processed using rolling/pilgering approaches. In all cases, atom probe tomography and energy-filtered transmission electron microscopy demonstrated that ODS structure survived multiple pilgering operations, and precipitate microstructure evolution matched well the state-of-the-art nanoprecipitate coarsening models.
Original language | English |
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Article number | 110333 |
Journal | Materials and Design |
Volume | 213 |
DOIs | |
State | Published - Jan 2022 |
Funding
The work presented in this paper was supported by the Advanced Fuels Campaign of the Nuclear Technology Research and Development program in the Office of Nuclear Energy, US Department of Energy (DOE). This manuscript has been authored by Oak Ridge National Laboratory (ORNL), managed by UT-Battelle, LLC, under Contract No. DE-AC05-00OR22725 with the DOE . A part of the microscopy research was conducted at the Center for Nanophase Materials Sciences, which is a DOE Office of Science User Facility. The authors would like to acknowledge Eric Manneschmidt for his assistance with mechanical property evaluations. The authors would like to thank James Burns and Jonathan Poplawsky at ORNL for assistance with atom probe tomography data collection. The authors would like to acknowledge Nippon Nuclear Fuel Development Co. Ltd, and particularly Kan Sakamoto, for their assistance in pilgering the OFRAC and CrAZY alloys. This manuscript has been authored by UT-Battelle LLC, under Contract No. DE-AC05-00OR22725 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy 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 presented in this paper was supported by the Advanced Fuels Campaign of the Nuclear Technology Research and Development program in the Office of Nuclear Energy, US Department of Energy (DOE). This manuscript has been authored by Oak Ridge National Laboratory (ORNL), managed by UT-Battelle, LLC, under Contract No. DE-AC05-00OR22725 with the DOE. A part of the microscopy research was conducted at the Center for Nanophase Materials Sciences, which is a DOE Office of Science User Facility. The authors would like to acknowledge Eric Manneschmidt for his assistance with mechanical property evaluations. The authors would like to thank James Burns and Jonathan Poplawsky at ORNL for assistance with atom probe tomography data collection. The authors would like to acknowledge Nippon Nuclear Fuel Development Co. Ltd, and particularly Kan Sakamoto, for their assistance in pilgering the OFRAC and CrAZY alloys. Data will be made available upon reasonable request.
Keywords
- Accident Tolerant Cladding
- Advanced Reactor Cladding
- Atom probe tomography (APT)
- Electron backscattered diffraction (EBSD)
- Mechanical properties
- Oxide dispersion strengthened (ODS) alloys
- Pilgering