Abstract
Neutron irradiation tests were carried out on 3D-printed SiC derived from binderjet additive manufacturing and chemical vapor infiltration. Irradiation was carried to 2.3 dpa over a temperature range of 400–850 °C. Anisotropy that had been observed in the thermal conductivity of 3D-printed SiC prior to irradiation vanished after irradiation as the irradiation defect thermal resistivity accumulated in the material. No degradation in strength was observed in the material before or after irradiation, at various temperatures, or in different orientations. Electron microscopy of the microstructure after neutron irradiation showed distinct defect morphologies in the heterogenous material, but no evidence for irradiation-induced cracking or degradation in the microstructure was observed.
Original language | English |
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Article number | 152980 |
Journal | Journal of Nuclear Materials |
Volume | 551 |
DOIs | |
State | Published - Aug 1 2021 |
Funding
The assistance and technical insights of Brian Jolly, Michael Trammell, Dylan Richardson, Austin Schumacher, Tom Geer, Michael McAlister, Stephanie Curlin, and Patrick Champlin at Oak Ridge National Laboratory (ORNL) are gratefully acknowledged. Yutai Katoh and Xunxiang Hu performed a thorough review of the manuscript. The efforts of ORNL's staff at the Irradiated Materials Examination and Testing (IMET) hot cell facility and the Low Activation Materials Design and Analysis Laboratory (LAMDA) are gratefully acknowledged. This work was supported by the Transformational Challenge Reactor program of US Department of Energy (DOE Office of Nuclear Energy. A portion of this research used resources at the High Flux Isotope Reactor, a DOE Office of Science User Facility operated by ORNL. The assistance and technical insights of Brian Jolly, Michael Trammell, Dylan Richardson, Austin Schumacher, Tom Geer, Michael McAlister, Stephanie Curlin, and Patrick Champlin at Oak Ridge National Laboratory (ORNL) are gratefully acknowledged. Yutai Katoh and Xunxiang Hu performed a thorough review of the manuscript. The efforts of ORNL's staff at the Irradiated Materials Examination and Testing (IMET) hot cell facility and the Low Activation Materials Design and Analysis Laboratory (LAMDA) are gratefully acknowledged. This work was supported by the Transformational Challenge Reactor program of US Department of Energy (DOE Office of Nuclear Energy. A portion of this research used resources at the High Flux Isotope Reactor, a DOE Office of Science User Facility operated by ORNL. This manuscript has been authored by UT-Battelle, LLC under Contract No. 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 ).
Funders | Funder number |
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U.S. Department of Energy | |
Office of Science | |
Office of Nuclear Energy | |
Oak Ridge National Laboratory |
Keywords
- Kurt Terrani
- ORNL
- Oak Ridge
- TN United States