Corrosion of oxide dispersion strengthened iron–chromium steels and tantalum in fluoride salt coolant: An in situ compatibility study for fusion and fusion–fission hybrid reactor concepts
Creators
- 1. Lawrence Livermore National Laboratory, Livemore, CA 94550 (United States)
- 2. Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto 611-0011 (Japan)
Description
Highlights: ► ODS steel corrosion in molten fluoride salts was studied in situ using electrochemical impedance spectroscopy. ► Steel/coolant interfacial resistance increases from 600 to 800 °C due to an aluminum enriched layer forming at the surface. ► The addition of tungsten to ODS steels increases corrosion resistance measurably at 600 °C. - Abstract: Primary candidate classes of materials for future nuclear power plants, whether they be fission, fusion or hybrids, include oxide dispersion strengthened (ODS) ferritic steels which rely on a dispersion of nano-oxide particles in the matrix for both mechanical strength and swelling resistance, or tantalum alloys which have an inherent neutron-induced swelling resistance and high temperature strength. For high temperature operation, eutectic molten lithium containing fluoride salts are attractive because of their breeding capability as well as their relatively high thermal capacity, which allow for a higher average operating temperature that increases power production. In this paper we test the compatibility of Flinak (LiF–NaF–KF) salts on ODS steels, comparing the performance of current generation ODS steels developed at Kyoto University with the commercial alloy MA956. Pure tantalum was also tested for comparative purposes. In situ data was obtained for temperatures ranging from 600 to 900 °C using a custom-built high temperature electrochemical impedance spectroscopy cell. Results for ODS steels show that steel/coolant interfacial resistance increases from 600 to 800 °C due to an aluminum enriched layer forming at the surface, however an increase in temperature to 900 °C causes this layer to break up and aggressive attack to occur. Performance of current generation ODS steels surpassed that of the MA956 ODS steel, with an in situ impedance behavior similar or better than that of pure tantalum.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.jnucmat.2011.07.036Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2011.07.036;
- PII
- S0022-3115(11)00776-8;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 419
- Journal Issue
- 1-3
- Journal Page Range
- p. 15-23
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43082955
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- ALUMINIUM; CHROMIUM STEELS; COOLANTS; CORROSION; CORROSION RESISTANCE; DISPERSIONS; ELECTROCHEMISTRY; FERRITIC STEELS; IMPEDANCE; LITHIUM FLUORIDES; MOLTEN SALTS; OXIDES; POTASSIUM FLUORIDES; SODIUM FLUORIDES; SWELLING; TANTALUM; TANTALUM ALLOYS; TEMPERATURE RANGE 0400-1000 K; TUNGSTEN
- Descriptors DEC
- ALKALI METAL COMPOUNDS; ALLOYS; CARBON ADDITIONS; CHALCOGENIDES; CHEMICAL REACTIONS; CHEMISTRY; CHROMIUM ALLOYS; DEFORMATION; ELEMENTS; FLUORIDES; FLUORINE COMPOUNDS; HALIDES; HALOGEN COMPOUNDS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LITHIUM COMPOUNDS; LITHIUM HALIDES; METALS; OXYGEN COMPOUNDS; POTASSIUM COMPOUNDS; POTASSIUM HALIDES; REFRACTORY METALS; SALTS; SODIUM COMPOUNDS; SODIUM HALIDES; STAINLESS STEELS; STEELS; TEMPERATURE RANGE; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.