A5023216840- Fusion materials and technologies
- Hydrogen embrittlement and corrosion behaviors in metals
- Nuclear Materials and Properties
- Microstructure and Mechanical Properties of Steels
- Non-Destructive Testing Techniques
- Metal and Thin Film Mechanics
- Ion-surface interactions and analysis
- Metallurgy and Material Forming
- Material Properties and Failure Mechanisms
- Microstructure and mechanical properties
- Thermodynamic and Structural Properties of Metals and Alloys
- High Temperature Alloys and Creep
- Heavy metals in environment
- Nuclear reactor physics and engineering
- Marine and coastal ecosystems
- Magnetic Properties and Applications
- Mercury impact and mitigation studies
- Muon and positron interactions and applications
- Fatigue and fracture mechanics
- Diamond and Carbon-based Materials Research
Suzhou Research Institute
2021-2024
China General Nuclear Power Corporation (China)
2023
Fudan University
2016
The prediction of irradiation-induced transition temperature shift for RPV steels is an important method long term operation nuclear power plant. Based on the irradiation embrittlement data, model developed with machine learning XGBoost. Then residual, standard deviation and predicted value vs. measured analysis are conducted to analyze accuracy this model. At last, Cu content threshold saturation values analysis, dependence, Ni/Cu dependence flux effect given verify reliability. Those...
Shear-coupled grain boundary motion (SCGBM) is an important and efficacious plasticity mechanism in the deformation of metals. In this work, a molecular dynamic (MD) simulation interaction between SCGBM Σ9[110](221) GB Cu-rich precipitates α-iron was carried out. The effects size, temperature, composition Cu were also studied. It found that inhibited significantly, configuration transformation from spheroid to ellipsoid investigated results. critical stress increased with size precipitates....
In order to investigate the correlation between irradiation-assisted stress corrosion cracking (IASCC) susceptibility and magnetic properties of austenitic stainless steel after ion irradiation, phase transformation were studied using a vibrating sample magnetometer synchrotron radiation grazing incidence X-ray diffraction (GIXRD) on an irradiated specimen up 25 displacements per atom. GIXRD indicated that body-centered-cubic (BCC) was introduced in by irradiation. Then, hysteresis loop...
The development of prediction model on irradiation embitterment (PMIE) reactor pressure vessel (RPV) is an important method for nuclear long term operation. Based the physical mechanism RPV embrittlement, a preliminary determined and critical threshold Cu content 0.072% obtained according to this model. Then named PMIE-2020 low steels developed. At last residual, standard deviation predicted values test distribution analysis are given. Simultaneously, comparison between other data provided....
Abstract Due to the extensive use of ferrite in nuclear power plants, thermal aging issues ferritic alloys have attracted significant attention. The present study investigates thermally aged FeCr binary with different Cr contents using various mechanical and magnetic properties tests. result indicates that increase element content prolonged significantly enhances strength alloy materials, along an important reduction toughness. Meanwhile, characteristic shows a considerable difference...
Abstract Stainless steel welds with a ferritic phase are extensively utilized in nuclear power plants. Spinodal decomposition stands as the primary factor contributing to degradation of their service performance. Ion irradiation has been widely employed investigate damage behavior materials. However, varying parameters, such dose rate and implanted ions, believed result significant differences extent spinodal decomposition. In this paper, proton experiments were conducted at different rates...
The reactor pressure vessel (RPV) is a critical barrier in nuclear power plants, but its embrittlement during service poses significant safety challenge. This study investigated the effects of Cu-enriched clusters on mechanical and magnetic properties Fe-0.9 wt.%Cu model alloys through thermal aging. Using Vickers hardness tests, Magnetic Barkhausen Noise (MBN) detection, Atom Probe Tomography (APT), aimed to establish quantitative correlation between MBN signals, hardness, clusters,...
The stress state of the primary circuit main pipeline is very complex mixed constant and periodic cyclic during operation nuclear power plants, which often affects failure behavior stainless steel (SS) pipe. fatigue 304LN SS under was investigated, it found that coupling effect has a significant collaborative acceleration on behavior. research results showed cracks in did not propagate even after 78 days both load conditions 5 KN 7.5 KN, while crack growth rate (CGR) specimen increased by...
Nitrogen ion implantation can be used to improve the surface mechanical properties of austenitic stainless steel. In this study, steel was irradiated with 1.1 MeV N ions at room temperature up 15 displacements per atom. Then microstructural and were studied by grazing incidence X-ray diffraction nano-indenter. A finer synchrotron radiation pattern is obtained compared traditional diffraction, indicating an expanded austenite phase γN CrN after being several damage levels. An...
Abstract The ferrite plays an important role in key component materials for nuclear power plant. study was performed on ferritic alloys with various Cr content ranging from 10 to 38wt%. Vickers-hardness and mechanical test results indicate that the high will cause a hardening strengthening effect steel. Meanwhile, it can be concluded alloy suffers reduction of toughness failure mode transition ductile brittle fracture increasing SEM fractography analysis.
The microstructure evolution of 5 MeV Xe20+ irradiation and the corrosion behavior postirradiation in Zr-4 Zr-1Nb alloys at room temperature high (≈ 360 °C) have been investigated. Positron results showed that vacancy defects precipitates are produced after irradiation, less defects, such as vacancies clusters, formed °C than resulting lower S parameters due to recombination defects. nanoindentation found both by lead hardening alloys. weight gain tests damage layer induced accelerates...
Abstract 6 MeV Xe ions were used to irradiate austenitic stainless steel at room temperature. Three displacement damage levels of 2,7 and 15 dpa selected. Microstructure surface morphology characterized by transmission electron microscopy (TEM), positron annihilation lifetime spectroscopy (PLS) atomic force microscope (AFM). PLS indicated that vacancy defects introduced irradiation. Vacancy clusters containing will reduce the lifetime. High density dislocation loops observed TEM. The size...
research-article Dislocation loop evolution in thermally aged 308SS weld metal by proton irradiation Share on Authors: Yuanfei Li Suzhou Nuclear Power Research Institute, China ChinaSearch about this author , Xiangbing Liu Chaoliang Xu Jian Yin Wangjie Qian Wenqing Jia Qiwei Quan Huajian Zhang Authors Info & Claims AIAM2021: 2021 3rd International Conference Artificial Intelligence and Advanced ManufactureOctober Pages 2394–2398https://doi.org/10.1145/3495018.3501110Online:14 March...