Dissolution of UO2 in molten Zircaloy-4. Pt. 4. Phase evolution during dissolution and cooling of 2000 to 2500 specimens
Creators
- 1. Atomic Energy of Canada Ltd., Pinawa, Man. (Canada). Whiteshell Labs.
Description
For pt.3 see ibid., vol.232, p.1-12, 1996. This report describes metallographic and scanning electron microscopy analyses of specimens from experiments to measure the solubility of unirradiated UO2 fuel in molten Zircaloy-4 at 2300, 2400 and 2500 C. The observed microstructures and individual phase analyses from specimens heated for up to 30 min at each temperature indicate that all melts became effectively saturated after a few minutes at temperature, in agreement with our findings from previous 2000-2200 C experiments. Although slow diffusion of oxygen from residual UO2 to the melt can, in theory, induce subsequent precipita tion of small quantities of a (U, Zr)O2-x phase over long time intervals, no evidence for precipitation was found in the microstructures and phase compositions. Thus, the observations support the contention that UO2 dissolution effectively ceases when the melt reaction path across the U-Zr-O phase diagram intersects the boundary of the two-phase [(U, Zr)O2-x+L] field. The saturated melt compositions have been used to revise the pseudo-binary Zr(O)-UO2 phase diagram, allowing more realistic prediction of the products formed by fuel/molten cladding interaction. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 232
- Journal Issue
- 1
- Journal Page Range
- p. 13-22.
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 28005764
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CANDU TYPE REACTORS; DIFFUSION; DISSOLUTION; FUEL-CLADDING INTERACTIONS; MELTDOWN; MICROSTRUCTURE; PHASE DIAGRAMS; PRECIPITATION; SCANNING ELECTRON MICROSCOPY; SOLIDIFICATION; SOLUBILITY; TEMPERATURE RANGE 1000-4000 K; URANIUM DIOXIDE; X-RAY FLUORESCENCE ANALYSIS; ZIRCALOY 4
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; ALLOY-ZR98SN-4; ALLOYS; CHALCOGENIDES; CHEMICAL ANALYSIS; CHROMIUM ADDITIONS; CORROSION RESISTANT ALLOYS; CRYSTAL STRUCTURE; DIAGRAMS; ELECTRON MICROSCOPY; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HEAVY WATER MODERATED REACTORS; INFORMATION; IRON ADDITIONS; MATERIALS; MICROSCOPY; NONDESTRUCTIVE ANALYSIS; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTORS; SEPARATION PROCESSES; TEMPERATURE RANGE; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; URANIUM COMPOUNDS; URANIUM OXIDES; X-RAY EMISSION ANALYSIS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS