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 Investigation on the evaporation rate of liquid lead and radioisotope retention capability of molten lead as coolant
Author(s) Shuprio Ghosh, Osman Anderoglu, Cemal Cakez, Khaled Talaat, Keith Woloshun, Michael Epstein, Sung Jin Lee, Paolo Ferroni, Emre Tatli, Matthew Memmott
On-Site Speaker (Planned) Shuprio Ghosh
Abstract Scope Uncertainties regarding the radionuclide retention properties of molten lead in accident conditions have hampered the safety assessment and licensing process of Lead Cooled Fast Reactors (LFRs). The radionuclide retention capability of molten lead is largely influenced by its chemical properties and fluidic movement inside the reactor vessel. Lead aerosol is produced by vaporization of lead and is released into the argon cover gas region. Fission products present in the coolant may also be released as additional components of the lead aerosol. This current research on lead evaporation rate aims to improve existing knowledge in predicting the radioisotope (e.g. I, Cs, Sr etc) release into the cover gas region in an accident scenario.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Mechanical Properties, 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
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