Corrosion of Candidate Materials in Molten FLiBe Salt for Fluoride-Salt-Cooled High-Temperature Reactor (FHR)
Creators
- 1. University of Wisconsin-Madison, 1500 Engineering Drive, Madison, WI, 53706 (United States)
- 2. Massachusetts Institute of Technology, 138 Albany Street, NW13-280, Cambridge, MA, 02139 (United States)
Description
Molten fluoride salts have attracted considerable attention because of their desirable thermophysical properties that lead to superior heat transfer. Recently, fluoride salts are being considered as coolants in the fluoride salt-cooled high temperature reactors (FHRs). The successes of the molten salt reactor experiment (MSRE) program in 1950's-70's at Oak Ridge National Laboratory (ORNL) has also driven the pursuit of molten salt nuclear reactor as one of the lead next generation nuclear reactor concepts. Unlike MSRE where the uranium fuel was dissolved in the molten fluoride salt, the FHR concept is expected to use molten salt (2LiF-BeF2, FLiBe) only as coolant in conjunction with solid TRISO fuel particles immersed in the molten salt. One of the important challenges in FHR development is corrosion of structural materials in high-temperature molten 2LiF-BeF2 (FLiBe) salt. Currently, 316 stainless steel (nominal composition: Fe-12Ni-17Cr-2.5Mo-1Si-2Mn-0.03C) and Hastelloy N (nominal composition: Ni-7Cr-16Mo-5Fe-1Si-0.8Mn) are deemed as promising candidate alloys for the construction of some of the structural components of FHR. 316 stainless steel is ASME code certified for high temperatures (up to 760 deg. C) applications. Hastelloy N has been shown to have outstanding corrosion resistance in molten FLiBe but present code certification data limit the use of this alloy to only about 704 deg. C. Modifications of Hastelloy N with higher creep strength are presently being developed at ORNL. Other materials such graphite, SiC/SiCf and C/Cf composites, are also considered for structural applications in the FHR. The presence of these multiple materials in a molten FLiBe salt medium can further exacerbate and complicate corrosion effects. Therefore, it is necessary to understand the corrosion behavior of these materials in molten FLiBe salt. The corrosion behavior of Hastelloy N, 316 stainless steel, and CVD SiC and two types of SiC-SiCf composites have been tested in molten FLiBe salt at 700 deg. C. When tested in metal-lined crucibles both Hastelloy N and 316 stainless steel showed very good corrosion resistance. Samples tested in graphite crucibles showed greater propensity for corrosion and carburization was observed in the near surface regions of the alloys. CVD SiC showed outstanding corrosion resistance. However, the two SiC-SiCf composites exhibited corrosion attack implying that the manufacturing process may play a role in the corrosion of these composites. (authors)
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 114
- Journal Issue
- 1
- Journal Page Range
- p. 1232-1234
- ISSN
- 0003-018X
Conference
- Title
- Annual Meeting of the American Nuclear Society. Embedded topical meeting 'Nuclear fuels and structural material for the next generation nuclear reactors'
- Dates
- 12-16 Jun 2016
- Place
- New Orleans, LA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52032393
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BERYLLIUM FLUORIDES; CARBURIZATION; CHEMICAL VAPOR DEPOSITION; COOLANTS; CORROSION; CORROSION RESISTANCE; CREEP; CRUCIBLES; FLIBE; FUEL PARTICLES; GRAPHITE; HASTELLOY N; HEAT TRANSFER; MOLTEN SALT REACTORS; SILICON CARBIDES; STAINLESS STEELS; TEMPERATURE RANGE 0400-1000 K; URANIUM
- Descriptors DEC
- ACTINIDES; ALKALINE EARTH METAL COMPOUNDS; ALLOY-NI70MO17CR7FE5; ALLOYS; ALUMINIUM ADDITIONS; ALUMINIUM ALLOYS; BERYLLIUM COMPOUNDS; BERYLLIUM HALIDES; CARBIDES; CARBON; CARBON ADDITIONS; CARBON COMPOUNDS; CHEMICAL COATING; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DEPOSITION; ELEMENTS; ENERGY TRANSFER; FLUORIDES; FLUORINE COMPOUNDS; HALIDES; HALOGEN COMPOUNDS; HARDENING; HASTELLOYS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICAL PROPERTIES; METALS; MINERALS; MOLTEN SALTS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NONMETALS; REACTORS; SALTS; SILICON COMPOUNDS; STEELS; SURFACE COATING; SURFACE HARDENING; SURFACE TREATMENTS; TEMPERATURE RANGE; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 4 refs.; Available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 United States