Thermophysical properties of molten FeO1.5, (FeO1.5)0.86-(ZrO2)0.14 and (FeO1.5)0.86-(UO2)0.14
Creators
- 1. Japan Atomic Energy Agency, Fast Reactor Cycle System Research and Development Center, Oarai, Ibaraki (Japan)
- 2. Mitsubishi Heavy Industries, Ltd., Nuclear Energy Systems, Reactor Core & Safety Engineering Department, Kobe, Hyogo (Japan)
- 3. Institut fuer Materialphysik im Weltraum, Deutsches Zentrum fuer Luft- und Raumfahrt (DLR), Koeln (Germany)
- 4. Osaka University, Graduate School of Engineering, Osaka (Japan)
Description
FeO1.5 is a promising candidate for a sacrificial material to lower the liquidus temperature of molten corium while keeping the viscosity as low as possible in order to mitigate the molten core-concrete interaction. Phase diagrams of such systems as FeO1.5-ZrO2 and FeO1.5-UO2 indicate that the FeO1.5 addition would significantly lower the liquidus temperature of corium, but how it would affect the viscosity has not been investigated. Thus, the viscosity of FeO1.5, (FeO1.5)0.86-(ZrO2)0.14, and (FeO1.5)0.86-(UO2)0.14 was measured using the aerodynamic-levitation technique coupled with the droplet-oscillation method. It was found that the viscosity of (FeO1.5)0.86-(ZrO2)0.14 at approximately 2100 K is almost identical to that of ZrO2 at around 3200 K, and that (FeO1.5)0.86-(UO2)0.14 maintains a low viscosity at a temperature well below the melting temperature of UO2, owing to the low viscosity of FeO1.5. These results indicate that the iron oxide addition would not only lower the liquidus temperature of the molten corium but also keep its fluidity as high as possible. (author)
Availability note (English)
Available from DOI: https://doi.org/10.1080/00223131.2022.2032445Additional details
Identifiers
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo) (Online)
- Journal Volume
- 59
- Journal Issue
- 9
- Journal Page Range
- p. 1139-1148
- ISSN
- 1881-1248
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 54024371
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- CARBON DIOXIDE LASERS; CORIUM; DROPLETS; HARMONIC OSCILLATORS; HEAT LOSSES; IRON OXIDES; MELTING POINTS; MOLTEN CORE-CONCRETE INTERACTIONS; PWR TYPE REACTORS; REACTOR VESSELS; SEVERE ACCIDENTS; VISCOSITY
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; CHALCOGENIDES; CONTAINERS; ENERGY LOSSES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; GAS LASERS; HEAT TRANSFER; IRON COMPOUNDS; LASERS; LOSSES; OXIDES; OXYGEN COMPOUNDS; PARTICLES; PHYSICAL PROPERTIES; POWER REACTORS; REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENT COMPOUNDS; TRANSITION TEMPERATURE; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 39 refs., 7 figs.