A self-consistent plasticity theory for modeling the thermo-mechanical properties of irradiated FCC metallic polycrystals |
| |
| Institution: | 1. State Key Laboratory for Turbulence and Complex System, Department of Mechanics and Engineering Science, College of Engineering, Peking University, Beijing 100871, PR China;2. CAPT, HEDPS and IFSA Collaborative Innovation Center of MoE, Peking University, Beijing 100871, PR China;3. State Key Laboratory of Nuclear Physics and Technology, School of Physics, Peking University, Beijing 100871, PR China;4. Department of Mechanics and Shanghai Institute of Applied Mathematics and Mechanics, Shanghai University, Shanghai 200444, PR China;5. State Key Laboratory for Mechanical Behavior of Materials, Xi''an 710049, PR China;6. Shanghai Key Laboratory of Mechanics in Energy Engineering, Shanghai, 200072, PR China;1. CEA, DEN, SRMA, F-91191 Gif-sur-Yvette, France;2. Laboratoire d’Etude des Microstructures, CNRS-ONERA, 29 av. de la Division Leclerc, 92322 Châtillon Cedex, France;3. SCK–CEN, Nuclear Materials Science Institute, Boeretang 200, B-2400 Mol, Belgium;1. Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM 87545, USA;2. School of Materials Science and Engineering, Georgia Institute of Technology, Atlanta, GA 30332, USA;3. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, GA 30332, USA;1. State Key Laboratory of Advanced Design and Manufacturing for Vehicle Body, Hunan University, Changsha, 410082, PR China;2. State Key Laboratory of Powder Metallurgy, Central South University, Changsha, 410083, PR China;3. Department of Materials Science and Engineering, The University of Tennessee, Knoxville, TN, 37996, USA;1. State Key Laboratory for Turbulence and Complex System, Department of Mechanics and Engineering Science, College of Engineering, Peking University, Beijing 100871, PR China;2. CAPT, HEDPS and IFSA Collaborative Innovation Center of MoE, BIC-ESAT, Peking University, Beijing 100871, PR China;3. Structural Material Group, Institute of Nuclear Materials Science, SCK CEN, Mol, Belgium |
| |
| Abstract: | A self-consistent theoretical framework is developed to model the thermo-mechanical behaviors of irradiated face-centered cubic (FCC) polycrystalline metals at low to intermediate homologous temperatures. In this model, both irradiation and temperature effects are considered at the grain level with the assist of a tensorial plasticity crystal model, and the elastic-visocoplastic self-consistent method is applied for the scale transition from individual grains to macroscopic polycrystals. The proposed theory is applied to analyze the mechanical behaviors of irradiated FCC copper. It is found that: (1) the numerical results match well with experimental data, which includes the comparison of results for single crystals under the load in different directions, and for polycrystals with the influences of irradiation and temperature. Therefore, the feasibility and accuracy of the present model are well demonstrated. (2) The main irradiation effects including irradiation hardening, post-yield softening, strain-hardening coefficient (SHC) dropping and the non-zero stress offset are all captured by the proposed model. (3) The increase of temperature results in the decrease of yield strength and SHC. The former is attributed to the weakened dislocation–defect interaction, while the latter is due to the temperature-strengthened dynamic recovery of dislocations through the thermally activated mechanism. The present model may provide a theoretical guide to predict the thermo-mechanical behaviors of irradiated FCC metals for the selection of structural materials in nuclear equipment. |
| |
| Keywords: | Polycrystalline material Constitutive behavior Thermo-mechanical process Irradiation effect Dislocations |
| 本文献已被 ScienceDirect 等数据库收录！ |
|
