Results 51 to 60 of about 2,606 (189)

Local reduced subspaces of subchannel‐inspired subdomains

International Journal for Numerical Methods in Engineering, Volume 125, Issue 18, 30 September 2024.
Abstract In this article, we study an update of the traditional subchannel approximation utilizing local reduced order bases. Through employing the symmetries and periodicity of a 7‐pin bundle, the global domain is decomposed into numerous repeating subdomains following several dividing strategies. We locally study the reduced basis generated by proper
Shenhui Ruan, Jorge Yanez, Andreas G. Class   +2 more
wiley   +1 more source

Screening of Filler Material for a Packed‐Bed Thermocline Energy Storage Test Facility with Lead–Bismuth Eutectic as the Heat Transfer Fluid

Energy Technology, Volume 12, Issue 2, February 2024.
Suitable solid filler materials are investigated for use in a packed‐bed heat storage test facility for high temperatures (500 °C) with lead–bismuth eutectic (LBE) as the heat transfer fluid. The thermophysical properties of six different candidate materials are investigated.
Franziska Müller‐Trefzer, Annette Heinzel, Robin Hesse, Alfons Weisenburger, Thomas Wetzel, Klarissa Niedermeier   +5 more
wiley   +1 more source

Source Term Calculation Method for Volatile Nuclides in Lead-bismuth Fast Reactor Based on Evaporation Experiments

Yuanzineng kexue jishu
Liquid lead-bismuth eutectic (LBE, 44.5%Pb-55.5%Bi), owing to its superior neutronic, physical, and chemical properties, serves as both a spallation neutron target material and a coolant for accelerator driven sub-critical system (ADS) and reactor ...
HUANG Liping, WANG Fenglong, ZHANG Qiang, WANG Shixi, ZHU Run, YANG Yong
doaj   +1 more source

High-Temperature Corrosion Behaviors of Structural Materials for Lead-Alloy-Cooled Fast Reactor Application

Applied Sciences, 2021
The corrosion of nuclear-grade steels in lead–bismuth eutectic (LBE) complicates the realization of high coolant temperatures. Corrosion tests of T91, HT9, and SS316L were performed in static cells at 600 °C for 2000 h at an oxygen level of 10−6 wt ...
Seung Gi Lee, Yong-Hoon Shin, Jaeyeong Park, Il Soon Hwang   +3 more
doaj   +1 more source

Influence of High-Density electropulsing treatment on the interface corrosion characteristics of 316L steel in Lead-Bismuth eutectic at 823 K [PDF]

E3S Web of Conferences, 2019
In order to find an effective method to improve the corrosion resistance properties of the candidate structural materials for lead-alloy cooled fast reactors, the 316L steel was treated by high density single elec-tropulsing.
Tian Shujian, Zhang Jianwu, Wang Yuying, Ma Yiyi, Wang Weishu   +4 more
doaj   +1 more source

Investigation of hydraulic performance and internal flow in a lead-bismuth coolant pump for nuclear reactors

Nuclear Engineering and Technology
The lead-cooled fast reactor (LFR) is a representative design of Generation IV nuclear reactors. To investigate the flow field characteristics of LFR coolant within an axial-flow pump, computational fluid dynamics (CFD) simulations were conducted for ...
Wentao Wang, Congxin Yang, Yanlei Guo, Tianzhi Lyu, Sen Zhao   +4 more
doaj   +1 more source

Electrochemical method for determining the solubility of impurities in lead-bismuth eutectic using molten salt electrolytes

Nuclear Engineering and Technology
Traditional physical methods for measuring solubility were often affected by viscosity, density, and surface tension. In this study, we selected appropriate electrolytes to determine the solubility of impurities in the lead-bismuth circuit at reactor ...
Taiqi Yin, Yongcheng Zhang, Lei Zhang, Tao Bo, Xiaoli Tan, Weiqun Shi   +5 more
doaj   +1 more source

Motion characteristics and drag coefficient of bubbles in liquid lead-bismuth eutectic

He jishu
BackgroundSteam generator tube rupture (SGTR) accidents in lead-bismuth cooled fast reactors result in the generation of numerous steam bubbles owing to the interaction of the high-temperature liquid lead-bismuth eutectic (LBE) from the primary circuit ...
LUO Haotian, LIU Li, YUAN Junjie, BAO Ruiqi, TIAN Xiaoyan, LI Da, GU Hanyang   +6 more
doaj   +1 more source

Fretting Wear and Corrosion in Liquid Lead-Bismuth Eutectic: A Review of Current State and Prospect

Engineered Science
Lead–bismuth eutectic (LBE) is a promising coolant for Generation-IV reactors. The corrosion of LBE and the fretting wear caused by fluid-induced vibration will gradually become the main causes of component failure.
Hui Chen, Guiyu Mei, Guangzhao Wang, Wei Tan, Guorui Zhu   +4 more
doaj   +1 more source

Improving the impermeability of nuclear graphite towards molten lead-bismuth eutectic in lead-cooled fast reactor by precursor impregnation and pyrolysis processes

Nuclear Engineering and Technology
The permeation of molten lead-bismuth eutectic (LBE) in graphite coolant channel material is a big issue that influences the stable operation of lead-cooled fast reactor (LFR).
Zhao He, Jinliang Song, Zhanjun Liu
doaj   +1 more source