| JOURNAL OF NUCLEAR MATERIALS | 卷:475 |
| High energy X-ray diffraction study of the relationship between the macroscopic mechanical properties and microstructure of irradiated HT-9 steel | |
| Article | |
| Tomchik, C.1  Almer, J.2  Anderoglu, O.3  Balogh, L.3,4  Brown, D. W.3  Clausen, B.3  Maloy, S. A.3  Sisneros, T. A.3  Stubbins, J. F.1  | |
| [1] Univ Illinois, Urbana, IL 61801 USA | |
| [2] Argonne Natl Lab, 9700 S Cass Ave, Lemont, IL 60439 USA | |
| [3] Los Alamos Natl Lab, POB 1663, Los Alamos, NM 87545 USA | |
| [4] Queens Univ, Kingston, ON K7L 3N6, Canada | |
| 关键词: Ferritic martensitic steel; HT-9; In-situ tensile test; High-energy X-ray diffraction; Lattice strain; Irradiation embrittlement; | |
| DOI : 10.1016/j.jnucmat.2016.03.023 | |
| 来源: Elsevier | |
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【 摘 要 】
Samples harvested from an HT-9 fuel test assembly (ACO-3) irradiated for six years in the Fast Flux Test Facility (FFTF) reaching 2-147 dpa at 382-504 degrees C were deformed in-situ while collecting high-energy Xray diffraction data to monitor microstructure evolution. With the initiation of plastic deformation, all samples exhibited a clear load transfer from the ferrite matrix to carbide particulate. This behavior was confirmed by modeling of the control material. The evolution of dislocation density in the material as a result of deformation was characterized through full pattern line profile analysis. The dislocation densities increased substantially after deformation, the level of dislocation evolution observed was highly dependent upon the irradiation temperature of the sample. Differences in both the yield and hardening behavior between samples irradiated at higher and lower temperatures suggest the existence of a transition in tensile behavior at an irradiation temperature near 420 degrees C dividing regions of distinct damage effects. (C) 2016 Elsevier B.V. All rights reserved.
【 授权许可】
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| Files | Size | Format | View |
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| 10_1016_j_jnucmat_2016_03_023.pdf | 2392KB |
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