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Du J, Jiang S, Cao P, Xu C, Wu Y, Chen H, Fu E, Lu Z. Superior radiation tolerance via reversible disordering-ordering transition of coherent superlattices. NATURE MATERIALS 2023; 22:442-449. [PMID: 35637339 DOI: 10.1038/s41563-022-01260-y] [Citation(s) in RCA: 5] [Impact Index Per Article: 5.0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Received: 08/10/2021] [Accepted: 04/18/2022] [Indexed: 06/15/2023]
Abstract
Materials capable of sustaining high radiation doses at a high temperature are required for next-generation fission and future fusion energy. To date, however, even the most promising structural materials cannot withstand the demanded radiation environment due to irreversible radiation-driven microstructure degradation. Here we report a counterintuitive strategy to achieve exceptionally high radiation tolerance at high temperatures by enabling reversible local disordering-ordering transition of the introduced superlattice nanoprecipitates in metallic materials. As particularly demonstrated in martensitic steel containing a high density of B2-ordered superlattices, no void swelling was detected even after ultrahigh-dose radiation damage at 400-600 °C. The reordering process of the low-misfit superlattices in highly supersaturated matrices occurs through the short-range reshuffling of radiation-induced point defects and excess solutes right after rapid, ballistic disordering. This dynamic process stabilizes the microstructure, continuously promotes in situ defect recombination and efficiently prevents the capillary-driven long-range diffusion process. The strategy can be readily applied into other materials and pave the pathway for developing materials with high radiation tolerance.
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Affiliation(s)
- Jinlong Du
- State Key Laboratory of Nuclear Physics and Technology, Department of Technical Physics, School of Physics, Peking University, Beijing, People's Republic of China
| | - Suihe Jiang
- Beijing Advanced Innovation Centre for Materials Genome Engineering, State Key Laboratory for Advanced Metals and Materials, University of Science and Technology Beijing, Beijing, People's Republic of China
| | - Peipei Cao
- Beijing Advanced Innovation Centre for Materials Genome Engineering, State Key Laboratory for Advanced Metals and Materials, University of Science and Technology Beijing, Beijing, People's Republic of China
| | - Chuan Xu
- State Key Laboratory of Nuclear Physics and Technology, Department of Technical Physics, School of Physics, Peking University, Beijing, People's Republic of China
| | - Yuan Wu
- Beijing Advanced Innovation Centre for Materials Genome Engineering, State Key Laboratory for Advanced Metals and Materials, University of Science and Technology Beijing, Beijing, People's Republic of China
| | - Huaqiang Chen
- State Key Laboratory of Nuclear Physics and Technology, Department of Technical Physics, School of Physics, Peking University, Beijing, People's Republic of China
| | - Engang Fu
- State Key Laboratory of Nuclear Physics and Technology, Department of Technical Physics, School of Physics, Peking University, Beijing, People's Republic of China.
| | - Zhaoping Lu
- Beijing Advanced Innovation Centre for Materials Genome Engineering, State Key Laboratory for Advanced Metals and Materials, University of Science and Technology Beijing, Beijing, People's Republic of China.
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Moses EI, de la Rubia TD, Storm E, Latkowski JF, Farmer JC, Abbott RP, Kramer KJ, Peterson PF, Shaw HF, Lehman RF. A Sustainable Nuclear Fuel Cycle Based on Laser Inertial Fusion Energy. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst09-34] [Citation(s) in RCA: 42] [Impact Index Per Article: 6.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Edward I. Moses
- Lawrence Livermore National Laboratory, 7000 East Ave., Livermore, CA 94550
| | | | - Erik Storm
- Lawrence Livermore National Laboratory, 7000 East Ave., Livermore, CA 94550
| | | | - Joseph C. Farmer
- Lawrence Livermore National Laboratory, 7000 East Ave., Livermore, CA 94550
| | - Ryan P. Abbott
- Lawrence Livermore National Laboratory, 7000 East Ave., Livermore, CA 94550
| | - Kevin J. Kramer
- Lawrence Livermore National Laboratory, 7000 East Ave., Livermore, CA 94550
| | - Per F. Peterson
- Lawrence Livermore National Laboratory, 7000 East Ave., Livermore, CA 94550
| | - Henry F. Shaw
- Lawrence Livermore National Laboratory, 7000 East Ave., Livermore, CA 94550
| | - Ronald F. Lehman
- Lawrence Livermore National Laboratory, 7000 East Ave., Livermore, CA 94550
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Abbott RP, Gerhard MA, Kramer KJ, Latkowski JF, Morris KL, Peterson PF, Seifried JE. Thermal and Mechanical Design Aspects of the LIFE Engine. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst18-8002] [Citation(s) in RCA: 19] [Impact Index Per Article: 2.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Ryan P. Abbott
- Lawrence Livermore National Laboratory, Livermore, CA, 94550
| | | | - Kevin J. Kramer
- Lawrence Livermore National Laboratory, Livermore, CA, 94550
| | | | - Kevin L. Morris
- Lawrence Livermore National Laboratory, Livermore, CA, 94550
- University of California, Berkeley, CA, 94720
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Cr incorporated phase transformation in Y 2O 3 under ion irradiation. Sci Rep 2017; 7:40148. [PMID: 28091522 PMCID: PMC5238390 DOI: 10.1038/srep40148] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Abstract] [Track Full Text] [Download PDF] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 09/01/2016] [Accepted: 11/11/2016] [Indexed: 11/08/2022] Open
Abstract
Under irradiation, chemical species can redistribute in ways not expected from equilibrium behavior. In oxide-dispersed ferritic alloys, the phenomenon of irradiation-induced Cr redistribution at the metal/oxide interfaces has drawn recent attention. Here, the thermal and irradiation stability of the FeCr/Y2O3 interface has been systematically studied. Trilayer thin films of 90 nm Fe - 20 at.% Cr (1st layer)/100 nm Y2O3 (2nd layer)/135 nm Fe - 20 at.% Cr (3rd layer) were deposited on MgO substrates at 500 °C. After irradiation, Cr diffuses towards and enriches the FeCr/Y2O3 interface. Further, correlated with Cr redistributed into the oxide, an amorphous layer is generated at the interface. In the Y2O3 layer, the original cubic phase is observed to transform to the monoclinic phase after irradiation. Meanwhile, nanosized voids, with relatively larger size at interfaces, are also observed in the oxide layer. First-principles calculations reveal that Cr substitution of Y interstitials in Y2O3 containing excess Y interstitials is favored and the irradiation-induced monoclinic phase enhances this process. Our findings provide new insights that may aid in the development of irradiation resistant oxide-dispersed ferritic alloys.
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