Results 61 to 70 of about 230 (172)

Peridynamic modeling of liquid metal dissolution corrosion in 316L stainless steel/Lead-Bismuth Eutectic systems

Nuclear Engineering and Technology
This paper develops a peridynamic framework for modeling liquid metal dissolution corrosion in 316L stainless steel/liquid lead-bismuth eutectic (LBE) systems. The proposed model integrates two dominant corrosion mechanisms: interfacial metal dissolution
Zhaoyang Song, Chenwen Tian, Zhikun Zhou, Juan Du, Ziguang Chen   +4 more
doaj   +1 more source

Irradiation accelerated lead-bismuth eutectic corrosion of the TiNbCrMoV high-entropy alloy coating: Effects of induced defects and grain growth

Materials & Design
In-depth understanding of the structural changes in high-entropy alloy (HEA) coating caused by irradiation is essential for comprehending the accelerated corrosion behavior.
Jiuguo Deng, Yudong Li, Yan Bai, Jijun Yang   +3 more
doaj   +1 more source

Influence of Si addition on the corrosion behavior of 9Cr ferritic/martensitic steel in static liquid lead-bismuth eutectic

Materials Research Express
This study investigated the corrosion behavior of 9Cr ferritic/martensitic (F/M) steel with varying silicon contents when exposed to static lead-bismuth eutectic (LBE) at temperatures between 450 °C and 550 °C.
Hao Liu, Qingsong Chen, Qingyu Li, Yongchun Li, Jijun Yang   +4 more
doaj   +1 more source

The corrosion behavior of AlOx coatings exposed to lead-bismuth eutectic at 350 °C–650 °C

Journal of Materials Research and Technology
The service life of heat-resistant materials is crucial for safe operation in the nuclear industry. Usually, it is necessary to coat the surface of the materials with a heat-resistant coating.
Xiteng Li, Yu Wang, Ke Zhao, Yongduo Sun, Jun Han, Xing Yin, Jun Wu, Yong Chen   +7 more
doaj   +1 more source

Tensile and cracking behavior of thin-walled 316Ti austenitic steel after exposure to 550 °C lead-bismuth eutectic with different oxygen concentration

Journal of Materials Research and Technology
The corrosion evolution of 316Ti steel in 550 °C lead-bismuth eutectic (LBE) with oxygen concentrations (Co) of 5 × 10−6 wt% and 5 × 10−8 wt% and their impact on the tensile behavior were investigated in this study.
Da Wang, Sirui Liu, Changquan Xiao, Bihan Sun, Wenjian Zhu, Xianfeng Ma, Jun Xiao   +6 more
doaj   +1 more source

Numerical simulation study on oxygen transport in the natural circulation process of liquid lead–bismuth eutectic

International Journal of Advanced Nuclear Reactor Design and Technology
The lead-cooled fast reactor uses liquid lead–bismuth eutectic (LBE) as the coolant. In accident conditions, a passive cooling system is used to remove the heat from the reactor core to avoid meltdown. Therefore, the natural circulation ability of liquid
Xiangdong Wang, Wentao Guo, Shengfei Wang, Haicai Lv, Fang Liu, Zhangpeng Guo   +5 more
doaj   +1 more source

Temperature-dependent degradation of Al2O3—CrAl-O—Cr-O—Al-O multilayer coatings on ferritic-martensitic steels in oxygen-saturated lead–bismuth eutectic

Materials & Design
The strong corrosiveness of lead–bismuth eutectic (LBE) to alloys significantly limits the development of lead-cooled fast reactors. Herein, a multilayer coating containing Al-O, Cr-O, CrAl-O, and Al2O3 layers were deposited on ferritic–martensitic steel
Jiaojiao Ma, Lili Xing, Jie Tan, Hui Wang, Xiujie He, Xing Yin   +5 more
doaj   +1 more source

Microstructural characteristics of the internal oxidation zone of ferritic/martensitic steel exposed to LBE at 550°C for 1000 h

Journal of Materials Research and Technology
The oxidation products formed on ferritic/martensitic (F/M) steel exposed to oxygen-saturated lead-bismuth eutectic (LBE) at 550 °C for 1000 h were investigated using various characterizations.
Hao Wang, Fujian Zhang, Jun Xiao, Linjiang Chai, Qi Xu, Xin Yin, Ke Zhao, Ning Guo, Zhongwen Yao, Shaoyu Qiu   +9 more
doaj   +1 more source

Corrosion Behavior of Ti₃SiC₂ in Flowing Liquid Lead-Bismuth Eutectic at 500 °C. [PDF]

Materials (Basel), 2022
Lyu L, Qiu X, Yue H, Zhou M, Zhu H.
europepmc   +1 more source

Recent Progress on Creep Properties of ODS FeCrAl Alloys for Advanced Reactors. [PDF]

Materials (Basel), 2023
Jia H, Wang Y, Wang Y, Han L, Zhang Y, Zhou Z.   +5 more
europepmc   +1 more source