Radiation induced grain boundary segregation in ferritic/martensitic steels

Xia, L.D.; Ji, Yanzhou; Liu, W.B.; Chen, H.; Yang, Zhigang; Zhang, C.; Chen, L.-Q.

doi:10.1016/j.net.2019.07.009

Cited by 14 publications

(6 citation statements)

References 32 publications

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“…However, the inhomogeneous thermodynamic and kinetic properties add challenges in simulations. For example, to capture the thickness of grain boundaries about few nanometers we have to use a small grid size l 0 (Piochaud et al, 2016;Xia et al, 2020). As we know that the time step for solving the diffusion equations can be estimated by dt l 2 0 /D 0 , where D 0 is the largest diffusivity of defects of interest.…”

Section: Conclusion and Discussionmentioning

confidence: 99%

“…The spatial dependent chemical potential μ GB j f (η) of species j on grain boundaries can be expressed as μ GB j f (η) ΔH GB j − TΔS GB j , where ΔH GB j and ΔS GB j are the difference of formation enthalpy and entropy due to the presence of grain boundaries, respectively. Low-angle symmetric tilt grain boundaries can be modeled by a wall of parallel edge dislocations (Hirth et al, 1968;Jiang et al, 2014;Xia et al, 2020). The elastic interaction between stress field associated with the dislocation array and point defects affect the formation (enthalpy) energy of species j near the grain boundaries.…”

Section: Chemical Potentialsmentioning

confidence: 99%

“…Phase-field approach is good at describing spatial and temporal evolution of chemistry and microstructure in a system with inhomogeneous thermodynamic and kinetic properties. Current phase-field models of RIS (Piochaud et al, 2016;Xia et al, 2020) in bicrystalline structure were extended from the rate theory. Like the rate theory, the sink strength of grain boundaries is derived by assuming that defects at sinks remain thermal equilibrium concentrations.…”

Section: Introductionmentioning

confidence: 99%

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Microstructure-Dependent Rate Theory Model of Radiation-Induced Segregation in Binary Alloys

Burkes

et al. 2021

Front. Mater.

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Conventional rate theory often uses the mean field concept to describe the effect of inhomogeneous microstructures on the evolution of radiation induced defect and solute/fission product segregation. However, the spatial and temporal evolution of defects and solutes determines the formation and spatial distribution of radiation-induced second phase such as precipitates and gas bubbles/voids, especially in materials with complicated microstructures and subject to high dose radiation. In this work, a microstructure-dependent model of radiation-induced segregation (RIS) has been developed to investigate the effect of inhomogeneous thermodynamic and kinetics properties of defects on diffusion and accumulations of solute A in AB binary alloys. Four independent concentrations: atom A, interstitial A, interstitial B, and vacancy on [A, B] sublattice are used as field variables to describe temporal and spatial distribution and evolution of defects and solute A. The independent concentrations of interstitial A and interstitial B allow to describe their different generation rates, thermodynamic and kinetic properties, and release the assumptions of interstitial generation and sink strength used in the conventional rate theory. Microstructure and concentration dependent chemical potentials of defects are used to calculate the driving forces of defect diffusions. With the model, the effects of defect chemical potentials and mobilities on the RIS in polycrystalline AB model alloys have been simulated. The results demonstrated the model capability in predicting defect evolution in materials with inhomogeneous thermodynamic and kinetic properties of defects. The model can be extended to materials with complicated microstructures such as a wide range of grain size distribution, coating structure and multiphases as well as radiation-induced precipitation subject to severe radiation damage.

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Section: Conclusion and Discussionmentioning

confidence: 99%

Section: Chemical Potentialsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Microstructure-Dependent Rate Theory Model of Radiation-Induced Segregation in Binary Alloys

Burkes

et al. 2021

Front. Mater.

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“…Advanced 9%-12%Cr ferritic/martensitic (F/M) steels including HT-9 (12Cr-1MoVW) have been considered as one of the most promising candidate reactor fuel cladding and structural materials in Generation IV advanced nuclear reactors, owing to their superior thermomechanical properties, irradiation resistance (void swelling and embrittlement) and corrosion resistance at elevated temperatures [1][2][3][4][5][6][7][8][9][10]. In the past few decades, a large amount of HT-9 steels have been widely studied all over the world.…”

Section: Introductionmentioning

confidence: 99%

Effects of Silicon Content and Tempering Temperature on the Microstructural Evolution and Mechanical Properties of HT-9 Steels

Liu

Hao

et al. 2020

Materials

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Two kinds of experimental ferritic/martensitic steels (HT-9) with different Si contents were designed for the fourth-generation advanced nuclear reactor cladding material. The effects of Si content and tempering temperature on microstructural evolution and mechanical properties of these HT-9 steel were studied. The microstructure of experimental steels after quenching and tempering were characterized by X-ray diffraction (XRD), scanning electron microscopy (SEM), and transmission electron microscopy (TEM); the mechanical properties were investigated by means of tensile test, Charpy impact test, and hardness test. The microscopic mechanism of how the microstructural evolution influences mechanical properties was also discussed. Both XRD and TEM results showed that no residual austenite was detected after heat treatment. The results of mechanical tests showed that the yield strength, tensile strength, and plasticity of the experimental steels with 0.42% (% in mass) Si are higher than that with 0.19% Si, whereas hardness and toughness did not change much; when tempered at 760 °C, the strength and hardness of the experimental steels decreased slightly compared with those tempered at 710 °C, whereas plasticity and toughness increased. Further analysis showed that after quenching at 1050 °C for 1 h and tempering at 760 °C for 1.5 h, the comprehensive mechanical properties of the 0.42% Si experimental steel are the best compared with other experimental steels.

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“…The biases (𝑌 #,99 : and 𝑌 #,99 * ) depend on the properties of sinks such as the misorientation angle of GBs [154][155][156], the coherency of the precipitate interface, and the pressure of gas bubbles. To investigate the effect of biases on gas bubble evolution, we carried out a parametric study by varying the biases.…”

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confidence: 99%

Microstructural-Level Fuel Performance Modeling of U-Mo Monolithic Fuel

Beeler

Cole

Kadambi

et al. 2021

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As the physics that governs the microstructural evolution of nuclear fuel span various time and spatial scales, to fully understand the fuel behavior inevitably involves atomic to mesoscale resolution that can be difficult to determine experimentally. Microstructural-level modeling and simulations can be used to develop physics-based materials models that can provide physical understanding to inform fabrication process control, as well as a valuable feedback mechanism between post-irradiation examination (PIE) results and fabrication parameters. In accordance with the program schedule, the primary goals of the microstructure modeling effort are to:1. Address critical microstructural questions and provide practical guidance to the fabricator via the fuel product specification 2. Provide mechanistic inputs for the existing fuel-performance code to improve its descriptive and predictive capability at the macroscopic scale.In fiscal year (FY)-21, the work scope consisted of six main facets: (1) the effect of carbides on fuel performance; (2) gas diffusivity in different phases; (3) integration of microstructural fuel-performance modeling; (4) property degradation; (5) irradiation creep; and (6) historical analysis of microstructure data. Brief summaries of each are included below.

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Radiation induced grain boundary segregation in ferritic/martensitic steels

Cited by 14 publications

References 32 publications

Microstructure-Dependent Rate Theory Model of Radiation-Induced Segregation in Binary Alloys

Microstructure-Dependent Rate Theory Model of Radiation-Induced Segregation in Binary Alloys

Effects of Silicon Content and Tempering Temperature on the Microstructural Evolution and Mechanical Properties of HT-9 Steels

Microstructural-Level Fuel Performance Modeling of U-Mo Monolithic Fuel

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