Results 21 to 30 of about 2,606 (189)
Corrosion behavior of ion-irradiated 12Cr2W2Mn F/M steel in liquid LBE
Nuclear Materials and Energy, 2021 The corrosion characteristics of 12Cr2W2Mn Ferritic/martensitic (F/M) steel before and after Au-ions irradiation in static lead–bismuth eutectic (LBE) have been investigated at 400 °C for 100 h.
Ke Shi +11 more
doaj +1 more source
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 A triangle subchannel model was established to study the flow and heat transfer characteristics of lead‐bismuth eutectic (LBE) alloy and the erosion rate of the core channel by the particulate in LBE. Under different inlet velocities, particle types, particle diameters, and particle concentrations, the erosion law of the channel wall in LEB was ...
Bingheng Zhu +3 more
wiley +1 more source
Processing of MAX phases: From synthesis to applications
Journal of the American Ceramic Society, Volume 104, Issue 2, Page 659-690, February 2021., 2021 Abstract MAX phases are a large family of materials with more than 150 different compositions that have been extensively investigated during the last 25 years. They present a layered structure and a unique combination of properties, bridging the gap between metallic and ceramic properties.
Jesus Gonzalez‐Julian
wiley +1 more source
Journal of Materials Research and Technology, 2023 The corrosion behavior of a series of FeCrAl alloys with four Cr contents was investigated in static oxygen-saturated liquid lead–bismuth eutectic (LBE) at 600 °C for 720 h.
Hui Wang +5 more
doaj +1 more source
Nuclear Materials and Energy, 2023 The AlCrFeTiNb monolayer coatings and the AlCrFeTiNb/(AlCrFeTiNb)N multilayer coatings are specially designed and prepared on ferritic/martensitic (F/M) steel cladding tube by magnetron sputtering technology, and their corrosion behavior in flowing (∼2 m/
Jian Yang +4 more
doaj +1 more source
Nuclear Engineering and Technology, 2021 Liquid lead-bismuth cooled fast reactor is one of the most promising reactor types among the fourth-generation nuclear energy systems. The flow and heat transfer characteristics of lead-bismuth eutectic (LBE) are completely different from ordinary fluids
Shaopeng He +5 more
doaj +1 more source
International Journal of Energy Research, Volume 44, Issue 5, Page 3295-3315, April 2020., 2020 Summary Simulation is becoming increasingly important in the safety analysis of nuclear reactors nowadays. The physical phenomena in a nuclear power plant happen on three classified scales: system scale (phenomenon over the whole plant is concerned), component scale (phenomenon in specific component is concerned), and mesoscale (phenomenon in a small ...
Kanglong Zhang
wiley +1 more source
Thermodynamic Analysis of High‐Temperature Energy Storage Concepts Based on Liquid Metal Technology
Energy Technology, Volume 8, Issue 3, March 2020., 2020 Herein, technical concepts for using liquid metal technology in innovative high‐temperature thermal energy storage (TES) systems are dealt with. Optimization strategies are presented for a reference case including transient behavior of the whole system.
Tim Laube +4 more
wiley +1 more source
Analysis of Resistance Characteristics of a 37 Rod Fuel Bundle under Low Reynolds Number
Journal of Energy, Volume 2020, Issue 1, 2020., 2020 During the working period of decay heat removal system, the flow rate of liquid sodium in wire‐wrapped fuel assembly is very low, generally Re < 1000. In the present study, both experimental methods and numerical simulation methods are applied. First, water experiment of 37‐pin wire‐wrapped rod bundle was carried out.
Yonghua Li +3 more
wiley +1 more source
Behaviour of short and long cracks in air and in liquid metal in T91 steel
MATEC Web of Conferences, 2018 The low cycle fatigue behaviour of a 9Cr1MoNbV martensitic steel has been investigated at 350°C in air and in lead-bismuth eutectic (LBE). Total strain controlled tests were performed from Δεt = 0.40% to 1.2%.
Vogt Jean-Bernard +3 more
doaj +1 more source