Results 31 to 40 of about 2,606 (189)

Degradation mechanism of oxide film on SIMP steel in LBE at temperatures above 550 °C

Nuclear Engineering and Technology
The corrosion behavior of SIMP steel in liquid lead-bismuth eutectic was investigated to elucidate the degradation mechanism of Fe-based protective oxide film in LBE when the temperature exceeds the critical threshold of 550 °C. Results show that a three-
Tao Liu, Chongdou Yang, Xiangrong Fan, Di Yun, Wenguan Liu, Miroslav Popovic, Bingyao Zhao, Haiqing Xia, Zhongbo Liu, Jie Qiu   +9 more
doaj   +1 more source

Assessment of Modified RELAP5 MOD3.2 Against LBE Natural Circulation Test Loops

Frontiers in Energy Research, 2021
Motivated by the significant natural circulation capability of lead–bismuth eutectic (LBE)–cooled systems, the RELAP5 MOD3.2 code was modified for the analysis of LBE-cooled reactors and non-nuclear systems.
Yufeng Lv, Xingmin Liu, Weihan Li, Chunqiu Guo, Zhiwei Zhou   +4 more
doaj   +1 more source

Investigation on numerical simulation models for heat transfer characteristics of lead-bismuth eutectic

International Journal of Advanced Nuclear Reactor Design and Technology
The liquid lead-bismuth eutectic (LBE) has distinct thermal and physical properties that challenge the effectiveness of traditional RANS turbulence models and turbulent Prandtl number (Prt) models for accurately simulating its flow and heat transfer ...
Zihan Qin, Ling Chen, Yongfa Zhang, Hao Qin   +3 more
doaj   +1 more source

CFD Analysis of Scaled Wire-wrapped rod Bundle Cooled by LBE [PDF]

E3S Web of Conferences, 2019
Lead bismuth eutectic (LBE) is one of the most potential materials for coolant for Lead based reactor and Accelerator Driven Systems (ADS). Thermal-hydraulic behaviour of LBE in fuel assembly is a key issue for development of the systems. To get a deeper
LYU Kefeng, SHENG Xuelei, MA Xudan, WANG Haitao   +3 more
doaj   +1 more source

Measurement and Analysis of Neutron Leakage Spectra from Pb and LBE Cylinders with D-T Neutrons

EPJ Web of Conferences, 2017
For validating the current evaluated neutron data libraries, neutron leakage spectra from lead and lead bismuth eutectic (LBE) cylinders have been measured using an intense D-T pulsed neutron source with time-of-flight (TOF) method by Institute of ...
Chen Size, Gan Leting, Li Taosheng, Han Yuncheng, Liu Chao, Jiang Jieqiong, Wu Yican   +6 more
doaj   +1 more source

Experimental Investigation of the Thermal Hydraulics in Lead Bismuth Eutectic-Helium Experimental Loop of an Accelerator-Driven System

Nuclear Engineering and Technology, 2016
The heat transfer characteristics between liquid lead bismuth eutectic (LBE) and helium are of great significance for the two-loop cooling system based on an accelerator-driven system (ADS).
Wenxuan Xi, Yongwei Wang, Xunfeng Li, Xiulan Huai, Jun Cai   +4 more
doaj   +1 more source

Effect of Irradiation on Corrosion Behavior of 316L Steel in Lead-Bismuth Eutectic with Different Oxygen Concentrations

Quantum Beam Science, 2021
In an accelerator-driven system (ADS), the beam window material of the spallation neutron target is heavily irradiated under severe conditions, in which the radiation damage and corrosion co-occur because of high-energy neutron and/or proton irradiation ...
Nariaki Okubo, Yuki Fujimura, Masakatsu Tomobe   +2 more
doaj   +1 more source

Corrosion of Stellite Alloys and WC‐Based Cemented Ceramics Exposed to Oxygen‐Containing Molten Pb at 600°C and 700°C

Energy Storage, Volume 8, Issue 1, February 2026.
ABSTRACT Liquid metals such as molten lead (Pb) are attractive heat transfer fluids for high‐temperature thermal energy storage systems. Although extensive research is performed on the corrosion behavior of structural steels and Fe‐based alloys in liquid Pb, the corrosion resistance of materials with high wear resistance in such environments is less ...
Anisa Purwitasari, Renate Fetzer, Annette Heinzel, Alfons Weisenburger, Georg Müller   +4 more
wiley   +1 more source

A CFD SSTk−ω−kθ−εθ four parameter heat transfer turbulence model for the 19-pin fuel assembly in LBE cooled reactors

Nuclear Engineering and Technology
Liquid lead-bismuth eutectic (LBE) alloy exhibits excellent thermo-hydraulic properties and chemical inertness as a coolant for fast reactors. Unlike conventional fluids such as water and air, LBE has a lower Prandtl number (Pr), and its local turbulent ...
YaoDi Li, Mei Huang, Yiyuan Du, Shiju Jin   +3 more
doaj   +1 more source

Thermal‐Hydraulic Characterization Preliminary Analysis of Pool‐Type Natural Circulation With Liquid Lead

International Journal of Energy Research, Volume 2026, Issue 1, 2026.
Lead‐cooled fast reactors are an important potential reactor type in the fourth‐generation nuclear energy system. And the clarity of the thermal‐hydraulic characteristics of pool‐type natural circulation is crucial for the design of lead‐based fast reactors.
Yang Liu, Xiangyang Wang, Lu Zhang, Hu Li   +3 more
wiley   +1 more source