ProgramMaster Logo
Conference Tools for 2021 TMS Annual Meeting & Exhibition
Register as a New User
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools
About this Abstract
Meeting 2021 TMS Annual Meeting & Exhibition
Symposium Corrosion in Heavy Liquid Metals for Energy Systems
Presentation Title Performance of Candidate Alloys at 500C in Flowing Lead
Author(s) Cemal Cakez, Shuprio Ghosh, Khaled Talaat, Keith Woloshun, Stuart Maloy, Cetin Unal, Michael Ickes, Paolo Ferroni, Osman Anderoglu
On-Site Speaker (Planned) Cemal Cakez
Abstract Scope A major obstacle to Lead Cooled Fast Reactor technology is the lack of structural materials that can withstand Pb corrosion at high temperatures (up to 700C) and flow velocities. Recently established lead loop facility at the University of New Mexico is capable of testing materials compatibility with flowing molten lead up to 3 m/s flow velocity. In this talk, results from the recent compatibility tests at 500C on a variety of engineering and model alloys including Fe-10Cr binary, ferritic FeCrSi and FeCrAl based alloys, and several austenitic steels including SS316 will be presented. The test conditions (oxygen levels in Pb, flow velocity, and temperature) are kept identical for each of these alloys during the tests. Initial analysis on 168- and 672-hour testing has been completed. The testing will be extended up to 4000 hrs. The results will also include long term lead/LBE compatibility testing of TIG and e-beam welded FeCrAl.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, High-Temperature Materials, Other


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
Lead Bismuth Eutectic Corrosion on Austenitic Stainless Steel
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)

Questions about ProgramMaster? Contact