Results 131 to 140 of about 230 (172)

Research progress on LBE corrosion-resistant coatings: A review

Progress in Nuclear Energy
Jiuguo Deng, Mingyang Zhou, Xi Qiu
exaly   +2 more sources

Research on Corrosion and Precipitation Behaviors in LBE Systems

Volume 6: Beyond Design Basis Events; Student Paper Competition, 2013
Liquid metal, mainly lead and lead-bismuth eutectic (LBE) has been widely applied in the advanced nuclear reactors and accelerator-driven transmutation (ADS) systems for a series of excellent physical and chemical properties, but LBE is very corrosive to the structural materials such as iron and stainless steel in medium and high temperature ...
Li Tian, Fenglei Nui, Sheng Gao, Yican Wu   +3 more
openaire   +1 more source

Review of the studies on fundamental issues in LBE corrosion

Journal of Nuclear Materials, 2008
Lead bismuth eutectic (LBE) technology is being developed for applications in advanced nuclear systems and high-power spallation neutron targets. In this paper, the current understanding of corrosion and the fundamental issues relevant to corrosion when using LBE as a heavy liquid metal nuclear coolant are reviewed.
Jinsuo Zhang, Ning Li
openaire   +1 more source

Corrosion experiments in flowing LBE at 450°C

Journal of Nuclear Materials, 2006
Abstract The corrosion behaviour of AISI 316L steel is being investigated in flowing lead–bismuth eutectic (LBE) at 450 °C. The tests are performed in the LECOR (lead corrosion) loop, at low oxygen activity in LBE. The preliminary results presented in this paper refer to AISI 316L stainless steel and show the start of a corrosion mechanism with a ...
G. Benamati, A. Gessi, Ping-Zhu Zhang
openaire   +1 more source

Study on corrosion of welded steel for LBE-cooled fast reactors

Progress in Nuclear Energy, 2011
Abstract Lead-bismuth eutectic (LBE) is a candidate coolant for fast reactors. Its physical, chemical and neutronic properties make it a prospect coolant for the reactors. However, corrosion of structure is the main problem of utilizing LBE as a coolant.
Asril Pramutadi Andi Mustari, Minoru Takahashi   +1 more
openaire   +1 more source

Screening of the FeCrAl LBE corrosion-resistant coatings: The effect of Cr and Al contents

Surface and Coatings Technology, 2023
Xi Qiu, Huifang Yue
exaly   +2 more sources

HLMIF, a facility for investigating the synergistic effect of ion-irradiation and LBE corrosion

Journal of Nuclear Materials, 2019
Abstract The synergistic effect of irradiation and Lead Bismuth Eutectic (LBE) corrosion on structural materials is of vital importance for the research and development of future lead cooled nuclear energy systems. A Heavy Liquid Metal and Irradiation Facility (HLMIF) was therefore designed and constructed at National Laboratory of Heavy ion ...
Hailong Chang, Lilong Pang, Jianrong Sun   +2 more
exaly   +2 more sources

Corrosion/precipitation in non-isothermal and multi-modular LBE loop systems

Journal of Nuclear Materials, 2004
Abstract Precise simulations of all hydrodynamic conditions encountered in practical lead–bismuth eutectic (LBE) coolant loop systems by use of flowing conditions in the laboratory are difficult and expensive, if not impossible. Therefore it is important and necessary to develop corrosion models to predict corrosion behaviors at the design stage of ...
Jinsuo Zhang, Ning Li
openaire   +1 more source

Fast‐flowing LBE corrosion of the SiC pump impeller: Numerical and experimental investigations

International Journal of Applied Ceramic Technology, 2022
Abstract In order to determine the stress state and the specific dynamic corrosion behaviors of the cooling pump impeller in the liquid lead‐bismuth eutectic alloy (LBE), the numerical and the experimental investigations on the fast‐flowing LBE corrosion behaviors of the SiC impeller were conducted.
Xianhui Li, Xian Zeng, Zhanchong Zhao, Xiaoxin Zhang, Qingzhi Yan, Youyuan Zhang, Yuying Wen, Xuanbing Yang, Feng Mao   +8 more
openaire   +1 more source

Corrosion behaviors of US steels in flowing lead–bismuth eutectic (LBE)

Journal of Nuclear Materials, 2005
Abstract Corrosion tests of several US martensitic and austenitic steels were performed in a forced circulation lead–bismuth eutectic non-isothermal loop at the Institute of Physics and Power Engineering (IPPE), Russia. Tube and rod specimens of austenitic steels 316/316L, D-9, and martensitic steels HT-9, T-410 were inserted in the loop. Experiments
Zhang, Jinsuo S., Li, Ning, Chen, Yitung, Rusanov, A. E.   +3 more
openaire   +1 more source