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Thermodynamic assessment of the Fe–Ni–Te system
KTH, School of Industrial Engineering and Management (ITM), Materials Science and Engineering.ORCID iD: 0000-0002-4501-695x
DEN-Service de Corrosion et du Comportement des Matériaux dans leur Environnement (SCCME), CEA, Université Paris-Saclay, Gif-sur-Yvette, F-91191, France.
DEN-Service de Corrosion et du Comportement des Matériaux dans leur Environnement (SCCME), CEA, Université Paris-Saclay, Gif-sur-Yvette, F-91191, France.
KTH, School of Industrial Engineering and Management (ITM), Materials Science and Engineering.ORCID iD: 0000-0001-5031-919X
2019 (English)In: Calphad, ISSN 0364-5916, E-ISSN 1873-2984, Vol. 67, article id 101672Article in journal (Refereed) Published
Abstract [en]

For the purpose of modeling internal corrosion of the stainless steel fuel pins in fast nuclear reactors, the present work presents a thermodynamic description of the Fe–Ni–Te system modeled via the Calphad method. The liquid phase was modeled using the ionic 2-sublattice liquid model. Only binary parameters were optimized in the β2, δ and τ solid phases, to fit the isothermal section at 600 °C. The liquid did not require much adjustment from the extrapolation from the binary Fe–Te, Ni–Te and Fe–Ni systems. The paper presents a re-optimization of the Fe–Te liquid description in order to remove inverted liquid miscibility gaps at high temperatures. The resulting phase diagrams reproduce experimental isothermal sections well, and fits liquidus and solidus data very well. The description will be incorporated into the Thermodynamics of Advanced Fuels - International Database (TAF-ID). This will then be coupled with the Germinal system code to model the fission-product induced corrosion in nuclear fuel pins.

Place, publisher, year, edition, pages
Elsevier, 2019. Vol. 67, article id 101672
Keywords [en]
Calphad, Fe–Ni–Te, Nuclear reactor materials, Phase diagrams, Thermochemistry, Thermodynamic modeling, Fission products, Internal corrosion, Isotherms, Nuclear fuels, Nuclear reactors, Steel corrosion, International database, Isothermal sections, Liquid miscibility gap, Reactor materials, Thermodynamic assessment, Thermodynamic description, Thermodynamic model, Liquids
National Category
Other Physics Topics Other Materials Engineering
Research subject
Materials Science and Engineering; Physics, Nuclear Engineering
Identifiers
URN: urn:nbn:se:kth:diva-263473DOI: 10.1016/j.calphad.2019.101672ISI: 000501935500007Scopus ID: 2-s2.0-85072259134OAI: oai:DiVA.org:kth-263473DiVA, id: diva2:1375489
Funder
Swedish Research Council
Note

QC 20191205

Available from: 2019-12-05 Created: 2019-12-05 Last updated: 2020-01-08Bibliographically approved

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Arvhult, CarlSelleby, Malin

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