Corrosion behavior of 316 stainless steel arc parts in liquid lead at 650 °C under high oxygen concentrations. [PDF]
Wang R +6 more
europepmc +1 more source
Wetting Behavior of LBE on Corroded Candidate LFR Structural Materials of 316L, T91 and CLAM. [PDF]
Zhu H +7 more
europepmc +1 more source
Liquid metal cooled fast reactor thermal hydraulic research development: A review. [PDF]
Agbevanu KT +3 more
europepmc +1 more source
ICONE11-36560 MODELING CORROSION IN OXYGENCONTROLLED LBE SYSTEMS
Li, Ning, Zhang, Jinsuo
openaire +1 more source
Ferritic/Martensitic (F/M) steel is regarded as a promising structural material for lead-cooled fast reactors due to its excellent radiation resistance and mechanical properties.However, its long-term service performance is significantly affected by two
ZHONG Yu-Xin +3 more
doaj
This study systematically investigated the influence of Au-ion irradiation (at damage doses of 5, 25, and 50 dpa) on the microstructure and lead-bismuth eutectic (LBE) corrosion resistance of 12Cr ferritic/martensitic steels.
Yudong Li +6 more
doaj +1 more source
Removal of the Homolog Tellurium of Polonium by SiO2 Nanofiber Filter for Lead Alloy-Cooled Reactors. [PDF]
Chen X +7 more
europepmc +1 more source
Cellular Automata Modeling as a Tool in Corrosion Management. [PDF]
Reinoso-Burrows JC +5 more
europepmc +1 more source
Impact of Bi content on the accuracy of oxygen concentration measurements in liquid Pb-Bi alloys. [PDF]
Zeng X +5 more
europepmc +1 more source
A novel approach on designing ultrahigh burnup metallic TWR fuels: Upsetting the current technological limits. [PDF]
Feng L +19 more
europepmc +1 more source

