Liquid metal corrosion

Slides:



Advertisements
Similar presentations
Filippo Parodi /Paolo Capobianco (Ansaldo Fuel Cells S.p.A.)
Advertisements

Pb and LBE: a technological comparison Alessandro Gessi, Mariano Tarantino, Pietro Agostini ENEA Cr Brasimone Camugnano, BO, Italy Matgen IV School,
DICTRA Mobility Database for Zr alloys C. Toffolon-Masclet, C. Desgranges and J.C. Brachet CEA Saclay, France C. Toffolon-Masclet et al., CALPHAD XLI,
Investigation of the Catalytic Activity of Plasma-Treated Fe, Ni, and Co Foil for Water Splitting Nick Lavrov, Olivia Watson.
Matter: Properties & Change
Structural response of SiC and PyC on swift heavy ion irradiation
Cr and Co release reduction from stainless steels in PWR and BWR 2009 ISOE Asia ALARA Symposium Aomori EPRI Radiation Protection Conference September 9,
1 NEG films: recent R&D progress Paolo Chiggiato (for the EST-SM-DA section) Vacuum Issues of the LHCb Vertex Detector 28 November NEG films: choice.
Materials Performance Centre Modeling Directions.
Introduction to Materials Science, Chapter 9, Phase Diagrams University of Virginia, Dept. of Materials Science and Engineering 1 Development of microstructure.
THERMODYNAMIC MODELLING OF INTERDIFFUSION IN Fe-Co AND Fe-Ni BONDS Matej Pašák.
Lead Technology Task 6.2 Materials for mechanical pump for HLM reactors M. Tarantino – ENEA Work Package Meeting – ENEA Bologna, November 17th, 2010.
Virtual Laboratory for Nanotechnology Applications 1) ENEA, Ente per le Nuove Tecnologie, l’Energia e l’Ambiente, Casaccia Research Centre, Via Anguillarese.
Corrosion and Compatibility in Advanced Reactor Systems ENVIRONMENT CANDIDATE MATERIALS liquid metals Na iron based alloys Pb-Bi iron based helium/graphite.
“Influence of atomic displacement rate on radiation-induced ageing of power reactor components” Ulyanovsk, 3 -7 October 2005 Displacement rates and primary.
MATERIALS FOR NUCLEAR APPLICATIONS CMAST (Computational MAterials Science & Technology) Virtual Lab Computational Materials.
Space Environment Neutral Environment Hydrogen
Distributions of fission products on PCI in spent PWR fuels using EPMA
Lead Technology Task 6.2 Materials for mechanical pump for HLM reactors M. Tarantino, I. Di Piazza, P. Gaggini Work Package Meeting Karlsruhe, November.
Introduction to Materials Science, Chapter 9, Phase Diagrams University of Virginia, Dept. of Materials Science and Engineering 1 Growth of Solid Equilibrium.
Composite materials with a network microstructure of α-Fe areas surrounded by continuous layer of iron phosphate compounds were prepared on the basis of.
Amino Acid Adhesion on TiO2 Surface DFT Model Francesco Buonocore Caterina Arcangeli, Massimo Celino, Ivo Borriello ENEA - C.R. Casaccia and NAST Centre.
Positron and Positronium Chemistry PPC10, September, Smolenice Castle, Slovakia Thermal annealing influence on ions implanted Fe-Cr model alloys.
NEEP 541 – Radiation Damage in Steels Fall 2002 Jake Blanchard.
Lead Alloy Corrosion R&D for Gen-IV S. Sharafat UCLA ITER TBM Meeting Agenda UCLA, Eng. IV – Conference Room September, 2004.
Numerical simulation of hydrogen dynamics at a Mg-MgH 2 interface Simone Giusepponi and Massimo Celino ENEA – C. R. Casaccia Via Anguillarese
MATERIAL ISSUES FOR ADS: MYRRHA-PROJECT A. Almazouzi SCKCEN, Mol (Belgium) On behalf of MYRRHA-TEAM and MYRRHA-Support.
The Nuts and Bolts of First-Principles Simulation Durham, 6th-13th December : Computational Materials Science: an Overview CASTEP Developers’ Group.
Control of Carbon Nanotube Nucleation Rate with a Hydrogen Beam Plasma Paolo Santos 1, Dorothée Alsentzer 3, Thomas B. Clegg 2,3, Sergio Lemaitre 2,3,
Development of EKINOX Model for the Prediction of Microstructural Evolutions in Zr Alloys during Oxydation L. Anagonou, C. Desgranges, C. Toffolon-Masclet,
Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Corrosion Investigations of Steels in Pb-Bi at FZK J. Konys, G. Müller, J. Knebel Materials -
10th ITPA conference, Avila, 7-10 Jan Changes of Deuterium Retention Properties on Metals due to the Helium Irradiation or Impurity Deposition M.Tokitani.
Materials Integration by Fission Reactor Irradiation and Essential Basic Studies for Overall Evaluation Presented by N.Yoshida and K.Abe At the J-US Meeting,
Updates of Iowa State University S. Dumpala, S. Broderick and K. Rajan Sep – 18, 2013.
Phase Diagrams melting / production process / alloying (strength, Tm...) heat treatment microstructure material properties system (e.g. Cu-Ni) components.
C2 Topic 1 Atomic Structure and the Periodic Table
First-principle simulations of structure and properties of metallic glasses V. Yu. Kazimirov FLNP JINR PAC for Condensed Matter Physics, Jan., 18, 2010.
Investigation of the Performance of Different Types of Zirconium Microstructures under Extreme Irradiation Conditions E.M. Acosta, O. El-Atwani Center.
3.17 Uses of electrolysis Purification of copper:
Characterization of Coal Ash by Materials Science Techniques R. J. Lauf Metals & Ceramics Division Oak Ridge National Laboratory.
1 Nanoscale Modeling and Computational Infrastructure ___________________________ Ananth Grama Professor of Computer Science, Associate Director, PRISM.
How to Use This Presentation
Basic Chemistry, Electrochemistry & Corrosion Theory
Ching-Rong “Ada” Chung Mentor: Dr. Jing Zhou Department of Chemistry
Corrosion What is Corrosion??? Prepared By Dr. Biswajit Saha.
ENT 487 ENVIRONMENTALLY ASSISTED CRACKING IN METALS
What is XPS? XPS (x-ray photoelectron spectroscopy) is also known as ESCA (electron spectroscopy for chemical analysis). XPS provides chemical information.
Chapter 11: Phase Diagrams
Introduction to Materials Science and Engineering
A Metallurgical Comparison of Mack T-12 Rod Bearings. Lots U, V & W
SPS1. Obtain, evaluate, and communicate information from the Periodic Table to explain the relative properties of elements based on patterns of atomic.
Abstract Questions Results Methods & Materials A Learning Process
Kinetics of Phase Transformations
Mass Transfer In Chemical Engineering
Atomistic simulations of contact physics Alejandro Strachan Materials Engineering PRISM, Fall 2007.
Atomistic materials simulations at The DoE NNSA/PSAAP PRISM Center
Group 2 Steels: Medium Carbon Alloy Steels (0.25 – 0.55 %C)
2/16/2019 9:54 PM Chapter 9 Phase Diagrams Dr. Mohammad Abuhaiba, PE.
IC AND NEMS/MEMS PROCESSES
Eutectic Type Phase Diagrams
TRL tables: power conversion and lifetime
Boriding Boronizing, also known as boriding, is a case hardening diffusion process where boron atoms are diffused into the surface of a metal component.
Multiscale Modeling and Simulation of Nanoengineering:
Kaustubh K. Rane Department of Materials Science and Engineering,
Modelling of IGSCC mechanism
XI Conference on Reactor Materials May , 2019, Dimitrovgrad
A.A. Urusov, A.A. Mokrushin, D.M. Soldatkin, K.K. Polunin
The Atomic-scale Structure of the SiO2-Si(100) Interface
XI Reactor Material Science Conference, Dimitrovgrad,
Presentation transcript:

Liquid metal corrosion Massimo Angiolini, Alessandro Gessi, Massimo Celino 4th Workshop on Nuclear Fe Alloys: Modeling and Experiment University of Edinburgh, Scotland 4th and 5th June 2013 ENEA Lungotevere Thaon di Revel, 76 00196 ROMA Italia

Introduction Lead and Lead–Bismuth Eutectic (LBE) have been proposed as candidate coolant materials for one class of the next generation nuclear reactors. They can also be used as both coolants and neutron spallation sources in the Accelerator Driven Systems low reactivity Lead is inert with respect to water, concrete etc. low vapor pressure Boiling temperature above melting point of the structural materials low viscosity good gamma shielding and high neutron yield Large density change with temperature decay heat removal by natural circulation

Introduction Lead and LBE at high temperature are very corrosive towards steels Compatibility of material with liquid lead is a key problem and represents the main issue in the development of lead and LBE-cooled systems. Corrosion in liquid lead follows two main processes depending on the concentration of oxygen dissolved in the melt: dissolution of the steel constitutive elements (preferential dissolution of some elements) reaction of the steel constitutive elements with the dissolved oxygen with the formation of an outer oxide scale not stable/internal oxidation Surface oxidation can be used to protect the steel from dissolution (Active Oxygen Control): maintaining a low level of oxygen in the liquid lead allow the formation of a protective oxide layer on the steel surface thus eliminating the direct contact between the steel and liquid lead Active Oxygen Control was found to work at relatively low temperatures but for temperatures above 500°severe corrosion attack are observed both in austenitic and F/M steels with the formation of thick oxide layers, which may spall off periodically leaving the steel surface exposed to the coolant Additional protection methods must be adopted to protect the parts of the reactor that operate at high temperature (cladding, spacers etc.) A better understanding of the corrosion mechanisms could lead to improve control of corrosion and the steel performance

Introduction In this context we propose the development of a model for the corrosion damage evolution for steels exposed  to liquid lead Development of reliable models of the system by using atomic- scale simulations, via classical or first-principle molecular dynamics techniques Use of transmission Electron Microscopy and Scanning Helium Ion Microscopy to gain microstructural information's at atomic level

Solubility and diffusivity data in liquid Pb and LBE Solubility data of iron in liquid Pb, Bi and LBE Solubility data of Fe, Cr, Ni in liquid Pb and LBE https://www.oecd-nea.org/science/reports/2007/nea6195-handbook.html

Solubility and diffusivity data in liquid Pb and LBE Data of oxygen solubility in lead [1982] Oxygen solubility in liquid lead obtained by electrochemical techniques at high temperature (2006) https://www.oecd-nea.org/science/reports/2007/nea6195-handbook.html

Solubility and diffusivity data in liquid Pb and LBE Iron diffusion coefficient in pure Pb and eutectic Pb-Bi (best fit 3 experimental points) Oxygen diffusion coefficient in liquid lead and lead-bismuth https://www.oecd-nea.org/science/reports/2007/nea6195-handbook.html

SEM Microstructural characterization T91 exposed to Pb, 10.000 hours of experiments, 500°C, Oxygen 10-6wt%. Weak, thick, quickly formed oxide scales, easily eroded by HLM flux. Alessandro Gessi, Mariano Tarantino, Pietro Agostini Matgen IV School, Santa Teresa, 21/9/2011

SEM Microstructural characterization AISI 316L specimens exposed for 2000 h in pure Pb, CHEOPE III Alessandro Gessi, Gianluca Benamati Journal of Nuclear Materials 376 (2008) 269–273

SEM Microstructural characterization SEM image of the D9 after (a) 1000 h and (b) 3000 h exposure to LBE P. Hosemann et al. Journal of Nuclear Materials 375 (2008) 323–330

Solubility and diffusivity values in liquid Pb and LBE Discrepancies regarding the solubility data for oxygen and to a lesser extent for iron Only a few data for the diffusion coefficients of metallic elements in liquid lead and lead bismuth are available The iron diffusion coefficient in Pb and Pb-Bi is known at only three temperatures There is a significant scatter of the different values of oxygen diffusion coefficient except in the 600-700°C temperature range No information's about compounds among the atomic species involved and/or contaminants Few information's about the microstructure: thickness of the oxidized regions and EDX concentrations profiles

Critical evaluation of the available experimental data Molecular modeling www.afs.enea.it/project/cmast Molecular dynamics codes Classical: Home-made code (second-moment empirical tight-binding) LAMMPS DL_POLY Ab-initio: CPMD (Car-Parrinello Molecular Dynamics) QE (Quantum Expresso) PCGamess Molecular dynamics simulation will be used to: Develop reliable models of liquid atomic scale structure of Pb and its alloys with low percentage of O, Cr, Ni, Fe etc. Characterize the liquid phase by computing: coordination number radial distribution function diffusion coefficient activation energy structure factor specific heat coefficient formation energy of aggregates and clusters etc Characterize the interface between liquid and selected surfaces (adhesion energy, defect energy, atomic structures near the surface, chemical bonding, etc.). Fit parameters from ab-initio modeling to develop classical interatomic potential for multiscale modeling Computational infrastructure ENEA-GRID infrastructure based on distributed computational environment. The GRID contains: the high performance parallel computing CRESCO platform, grid services for collaborative work, databases, etc. www.cresco.enea.it Critical evaluation of the available experimental data

Molecular modeling www.afs.enea.it/project/cmast Atomic scale modeling of materials via classical or ab-initio molecular dynamics approaches Liquid Lead and Lead–Bismuth Eutectic (LBE) characterization Iron corrosion in liquid Lead Pb-Pb M.Celino, R.Conversano, V.Rosato, “Atomistic simulation of liquid lead and lead-bismuth eutectic”, J. Nuclear Materials 301 (2002) 64-69 A.Arkundato, Z.Suud, M.Abdullah, W.Sutrisno, M.Celino, “Numerical study: iron corrosion-resistance in lead-bismuth eutectic coolant by molecular dynamics method”, Int. Conf. on Advances in Nuclear Science and Engineering ICANSE2011, AIP Conference Proceedings 1448 (2012) 155-163 A.Arkundato, Z.Suud, M.Abdullah, W.Sutrisno, M.Celino, “Molecular dynamics simulation of iron corrosion-reduction in high temperature molten lead using oxygen injection”, submitted

Microstructural investigations in support of modeling To this date, high resolution investigations of the microstructural details of lead corrosion are scarce TEM investigations provide a better description and understanding of the observed microstructure which will help in modeling the oxidation/erosion mechanism Diffraction contrast, EDX, EELS, Microdiffraction, HRTEM Phase changes due to dissolution of alloy components: for example formation of ferritic regions on austenitic steel due to dissolution of Ni Small voids/pores at the interface metal oxide layer or between the layers of the duplex oxide scale (inner Fe2.3Cr0.7O4 spinel layer and an upper magnetite layer) Small voids/pores in the steel due to dissolution of alloy components Microstructural details of the oxide scales Structure of the internal oxidation zone

Microstructural investigations in support of modeling Scanning He-Ions Microscopy will be used to provide images with a resolution of few angstroms on a larger scale and on bulk samples We will consider in our study 15-15 Ti and 316 austenitic steels that are at present the candidate materials for the realization of liquid lead fast reactors Investigations will be carried out on cross sectional samples of steel exposed to liquid lead varying: Temperature Oxygen content of the melt Time

Thank you for your kind attention