Study on the irradiation effect of mechanical properties of RPV steels using crystal plasticity model

Nie, Junfeng; Liu, Yunpeng; Xie, Qihao; Liu, Zhanli

doi:10.1016/j.net.2018.10.020

Cited by 19 publications

(11 citation statements)

References 26 publications

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“…Similar model for FCC metals was presented in [70]. However, contrary to [69], where the mobile and immobile dislocation densities were tracked separately, here edge and screw dislocation populations are divided. Since the SFTs are basic irradiation-induced defects in FCC metals, the defect evolution model based on [19] was applied.…”

Section: Of 17mentioning

confidence: 99%

“…Another DDCP model was reported in [69]. The dislocation density based crystal plasticity hardening model shares common concepts with the paper of [20], although some ot the effects (concentrations of point defects, cross slip and climb terms in evolution equations for dislocation densities, annihilation of immobile dislocation due to interaction with loops) are disregarded.…”

Section: Of 17mentioning

confidence: 99%

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Modelling Irradiation Effects in Metallic Materials using the Crystal Plasticity Theory

Frydrych¹

2023

Preprint

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The review starts by highlighting the significance of nuclear power plants in contemporary world, especially its indispensable role in the global efforts to reduce CO2 emissions. Then, it describes the impact of irradiation on microstructure and mechanical properties of reactor structural materials. The main part provides the reader with a thorough overview of crystal plasticity models developed to address the irradiation effects so far. All three groups of most important materials are included. Namely, the Zr alloys used for fuel cladding, austenitic stainless steels used for reactor internals and ferritic steels used for reactor pressure vessel. Other materials, especially those considered for construction of future fission and fusion nuclear power plants, are also mentioned. The review pays also special attention to ion implantation and instrumented nanoindentation which are a common way to substitute costly and time-consuming neutron irradiation campaigns.

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Section: Of 17mentioning

confidence: 99%

Section: Of 17mentioning

confidence: 99%

Modelling Irradiation Effects in Metallic Materials using the Crystal Plasticity Theory

Frydrych¹

2023

Preprint

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“…An irradiation crystal plasticity finite-element method (CPFEM) was developed to simulate the mechanical properties of irradiated materials by combining the crystal plasticity model and finite element platform. Nie et al summarized the crystal plasticity finite-element method (CPFEM) for body-centered cubic (BCC) crystals and successfully simulated the nano-indentation hardness of Chinese A508-3 steels with ion irradiation (Nie et al, 2019). Xiao et al (2015) developed a theoretical model to determine the mechanical behavior of facecentered cubic (FCC) polycrystals with nanotwins from the perspective of crystal plasticity.…”

Section: Introductionmentioning

confidence: 99%

Irradiation Effect on F321 Austenitic Stainless-Steel: Nanoindentation and Modeling With the Crystal Plasticity Method

2022

Self Cite

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In this study, 3.5 MeV Fe-ion irradiation experiments were conducted on F321 austenitic stainless-steel at different temperatures and doses. The nanohardness of the unirradiated and irradiated samples was characterized by performing nanoindentation experiments. Irradiation softening and hardening were clearly observed at 20, 100, and 300°C. However, at 300°C, after irradiation softening, the nanohardness first increased and then decreased, as opposed to the nanohardness at 20 and 100°C, which increased as the dose increased. In addition, a crystal plasticity model for a face-centered cubic single-crystal while considering irradiation-induced hardening has been proposed and numerically implemented in the user-material subroutine UMAT of ABAQUS. This was done to simulate the load-depth data of the nanoindentation experiment. The simulated results of the non-irradiated and irradiated F321 austenitic stainless-steel were compared with the experimental data. A good agreement was observed, which demonstrates the effectiveness and accuracy of the model.

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“…Brittle failure poses the greatest threat to the reactor. A large number of studies have shown that after long-term neutron irradiation at 288 • C, the impurity element Cu in the RPV steel will be precipitated as a Cu-rich nanometer phase, which is the main reason for the increase in tough-brittle transition temperature of RPV steel [9][10][11][12][13][14][15][16].…”

Section: Introductionmentioning

confidence: 99%

Atomic Simulations for Packing Changes of Nano-Sized Cu Clusters Embedded in the Febulk on Heating

Zhang

2021

Metals

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Understanding of the defect evolution mechanism under irradiation is very important for the research of pressure vessel steel embrittlement. In this paper, the embedded atom method (EAM) based canonical ensemble molecular dynamics (MD) method was used to study the evolution of the stacking structure of different nano-sized Cun (n = 13, 43 and 87) clusters in an Febulk embedded with BCC lattice structure during continuous heating. The mean square displacement, pair distribution functions and atomic structures of Cu atom clusters at the nanometer scale were calculated at different temperatures. The structural changes present apparent differences, for the Febulks contain nano-sized Cu clusters with different atom numbers during heating. For the Febulk–Cu13 system, since the ability to accommodate the atomic Cu in the Fe substrate is lesser, a small number of Cu atoms in BCC lattice positions cannot influence the whole structure of the Fe-Cu system. For the Febulk–Cu43 system, with an increase in temperature, a Cu atomic pile structural change happened, and the strain areas decreased significantly in the Febulk, but a single strain area grew large. For the Febulk–Cu87 system, when the Cu atoms are constrained by the Fe atoms in bulk, only a few of the Cu atoms adjust their positions. With the increase in temperature, strain in the Fe eased.

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Study on the irradiation effect of mechanical properties of RPV steels using crystal plasticity model

Cited by 19 publications

References 26 publications

Modelling Irradiation Effects in Metallic Materials using the Crystal Plasticity Theory

Modelling Irradiation Effects in Metallic Materials using the Crystal Plasticity Theory

Irradiation Effect on F321 Austenitic Stainless-Steel: Nanoindentation and Modeling With the Crystal Plasticity Method

Atomic Simulations for Packing Changes of Nano-Sized Cu Clusters Embedded in the Febulk on Heating

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