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Meeting 2021 TMS Annual Meeting & Exhibition
Symposium Corrosion in Heavy Liquid Metals for Energy Systems
Presentation Title Exposure Tests of Different Materials in Liquid Lead for LFRs: Effect of the Dissolved Oxygen on Corrosion
Author(s) Serena Bassini, Camillo Sartorio, Andrea Antonelli, Sebastiano Cataldo, Angela Fiore, Massimo Angiolini, Daniele Martelli, Micheal Ickes, Paolo Ferroni, Ivan Di Piazza, Mariano Tarantino
On-Site Speaker (Planned) Serena Bassini
Abstract Scope Corrosion studies in high-temperature liquid Pb of conventional materials such as Fe-Cr and Fe-Cr-Ni steels for LFRs have demonstrated that they are prone to corrode affecting their structural integrity. Corrosion is minimized by using oxygen in Pb to form protective Fe-Cr oxide layer on steels, but its protectiveness well works only up to 450-480 C limiting their applicability in LFRs. The present work shows preliminary corrosion results of new materials (Ni alloys, FeCrAl ODS, Zr and Mo alloys, and SiC) for potential use in Pb, obtained by ENEA and Westinghouse Electric Company. Tests were performed in static Pb at 550 and 750 C and different oxygen concentrations. The results demonstrated the potential availability in Pb of some of these materials, and confirmed the key influence of oxygen on corrosion, imposing oxygen control in Pb coolant to prevent critical damage of materials. About oxygen control, some ENEA activities will be illustrated.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, High-Temperature Materials, Characterization

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Anubis Multiphysics: A Neutronics-Thermal Hydraulics Coupling Platform for Flow Accelerated Corrosion Modeling in Reactor Conditions
Behaviour of spallation, activation and fission products in LBE
Compatibility of Alumina-Forming Austenitic Steels in Static and Flowing Pb
Corrosion behaviour and microstructural stability of alumina-forming austenitic steels exposed to oxygen-containing molten lead
Corrosion Investigations of Materials in Antimony-Tin And Antimony-Bismuth Alloys For Liquid Metal Batteries
Corrosion of Refractory Metals and Advanced Steels in Lead-Bismuth Eutectic
Electromagnetic Flow Sensor for Heavy Liquid Metals for Energy Systems
Engineering Model of the Kinetics of the Steel Oxide Layer in A Flow of a Heavy Liquid Metal Coolant Under Various Oxygen Conditions
Exposure Tests of Different Materials in Liquid Lead for LFRs: Effect of the Dissolved Oxygen on Corrosion
Fundamental Interactions of Steels and Nickel-based Alloys with Lead-based Liquid Alloys or Liquid Tin
In-Situ Crack Growth Testing in a Liquid Metal Environments
Investigation on the evaporation rate of liquid lead and radioisotope retention capability of molten lead as coolant
Liquid metal embrittlement of Al-containing high-entropy alloys exposed to lead-bismuth eutectic
Material Needs and Developments for the Westinghouse Lead Fast Reactor
Materials Compatibility Testing with Molten Lead up to 700C
Numerical and Analytical Researches of the Formation and Accumulation of Deposits on the Circuit with HLM Coolant within the Consistent Model for Physical and Chemical Processes
Numerical modelling of coolant chemistry in lead bismuth eutectic cooled nuclear reactors
Oxide Growth Modeling in Fe-Cr-Al Alloys: A Current Review
Performance of Candidate Alloys at 500C in Flowing Lead
PILLAR: Pool-type Integral Leading facility for Lead-alloy cooled Advanced small modular Reactor, and Its Use for Natural Convection Study and Corrosion
Preliminary results on the compatibility of Fe-Cr-Al and Fe-Cr-Al-Mo steels with liquid sodium at 700 C.
Progress in LBE chemistry control and measurement techniques for MYRRHA
Review of Liquid Metal Corrosion Under Irradiation and Progress Report on the LBE-Irradiation-Corrosion Experiment (ICE)

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