Results 41 to 50 of about 230 (172)

Lead-bismuth eutectic corrosion behavior of 9Cr ferritic/martensitic steel with different Si contents after Au-ion irradiation

Materials Research Express
Ferritic/martensitic (F/M) steels are considered optimal candidates for utilization as structural materials in Lead-Cooled Fast Reactor (LFR) due to their excellent mechanical properties at high temperatures and outstanding resistance to irradiation ...
Hao Liu, Sha Zhao, Yining Ren, Wei Zhang, Rongshuo Wang, Feifei Zhang, Jijun Yang   +6 more
doaj   +1 more source

Natural Convection Heat Transfer Analysis With Different DHX Operation Conditions of Sodium‐Cooled Fast Reactor Using ATHLET Code

Science and Technology of Nuclear Installations, Volume 2026, Issue 1, 2026.
Sodium‐cooled fast reactor (SFR) is one of the fourth‐generation nuclear reactor types, which has inherent safety features such as low corrosion and no severe interaction between molten fuel and sodium. However, the severe accident of core melting in SFR needs to be considered.
Yingying Huo, Qing Yang, Xiaojing Liu, Arnab Biswas   +3 more
wiley   +1 more source

Study on Corrosion and Thermal Alteration of Low‐Cost Storage Materials for Use in High‐Temperature Thermal Energy Storage Systems With Lead as the Heat Transfer Fluid

Energy Storage, Volume 7, Issue 8, December 2025.
ABSTRACT Liquid metal packed‐bed thermal energy storage (TES) can improve industrial waste heat recovery due to its wide operating temperature range and high thermal conductivity. However, reducing costs, especially for storage media, is essential for broader adoption.
Margaux Zehnder, Anisa Purwitasari, Annette Heinzel, Klarissa Niedermeier   +3 more
wiley   +1 more source

Improved corrosion resistance of TiAlCrNbMo alloy to lead-bismuth eutectic by pre-oxidation

Journal of Materials Research and Technology
A Ti48.5Al46Cr3Nb0.5Mo2 alloy was designed and fabricated to investigate its corrosion resistance to static liquid lead-bismuth eutectic (LBE). The microstructure and corrosion behavior of un-oxidized and pre-oxidized samples were compared.
Y. Liu, H.E. Ge, Q.S. Ren, H.W. Deng, Z. Li, B. Du, T. Zhang   +6 more
doaj   +1 more source

Frontiers of Synchrotron Methods for Actinide Science

Chemistry–Methods, Volume 5, Issue 8, August 2025.
This article explores the application of synchrotron radiation techniques ‐ XAS, XES, HERFD, RIXS, and XRD ‐ to investigate actinide materials. It provides insights into electronic structures, oxidation states, and phase transitions, emphasizing the transformative role of these techniques in advancing nuclear materials research, environmental safety ...
Damien Prieur, Lucia Amidani, Elena F. Bazarkina, Christoph Hennig, Eleanor Lawrence Bright, Andre Rossberg, Clara L. Silva, Kristina O. Kvashnina   +7 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

Corrosion behavior of electron beam welded 9Cr ferritic/martensitic steel in a liquid lead–bismuth eutectic at 550 °C

Nuclear Materials and Energy
The corrosion resistance of welded joints in a lead–bismuth eutectic (LBE) environment is crucial for the development of lead-cooled fast reactors (LFRs), as the welded joints typically exhibit more severe corrosion damage than the base material (BM ...
Yanyun Zhao, Shiao Ding, Boyang Zhang, Pan Yang, Yuanwei Sun, Man Jiang, Muyi Ni   +6 more
doaj   +1 more source

Erosion–corrosion behaviors of P91 steel in high-velocity flowing lead–bismuth eutectic

工程科学学报
Lead–bismuth eutectic (Pb–Bi) alloy, a liquid heavy metal, has garnered substantial attention as a candidate coolant for next-generation lead-cooled fast reactors (Gen-IV LFRs) and accelerator-driven systems (ADSs) owing to its exceptional nuclear and ...
Jisheng LI, Yanfei WANG, Xianzong WANG
doaj   +1 more source

Microstructural differences of oxide layer on Si-containing austenitic stainless steel exposed to oxygen-saturated and oxygen-poor LBE

Journal of Materials Research and Technology
Increasing the content of Si element in austenitic stainless steels is a strategic approach to improve their dissolution corrosion resistance in liquid lead-bismuth eutectic (LBE) at elevated temperature.
Hao Ren, Xiaoxin Zhang, Xian Zeng, Xiaodong Huang, Decang Zhang, Jun Zhang, Qingzhi Yan   +6 more
doaj   +1 more source

Corrosion and Small Sample Tensile Behavior of Ferritic/Martensitic Steel in Oxygen Saturated Lead-bismuth Eutectic

Yuanzineng kexue jishu
Ferritic/martensitic (F/M) steels are potentially applied as structural materials in the lead cooled fast reactor, a promising fourth-generation reactor that adopts lead-bismuth eutectic (LBE) as coolant.
LI Shijiang1, GONG Aoxiang1, SUN Lu1, MA Yan1, QIN Bo2, LONG Bin2, TONG Zhenfeng1,
doaj   +1 more source