journal article·2019-12Open access

TEM characterization of high burnup fast-reactor MOX fuel

Riley Parrish, Alexander Winston, Jason Harp, Assel Aitkaliyeva

Abstract

Abstract This work examines the radial evolution of a high burnup fast reactor mixed-oxide (MOX) fuel pellet irradiated at the Fast Flux Test Facility (FFTF) using scanning (SEM) and transmission electron microscopy (TEM). At 21.3% fissions per initial metal atoms (FIMA), the sample analyzed in this work is likely among the highest burnup oxide fuel samples ever evaluated using TEM. Initial SEM examination focused on the characterization of the fuel microstructure and solid fission product behavior as a function of radial position. The fuel pellet underwent extensive restructuring as demonstrated by columnar grain formation near the central void. Oxide fission product phases were confined to near the fuel centerline and decomposed from perovskite BaZrO3 to the fluorite ZrO2 type crystal structure. Metallic five metal precipitates (FMPs) were observed at all radial positions and the Pd-rich metallic phase increased in area fraction moving toward the pellet surface. TEM examination focused on the determination of dislocation density ranging from the fuel pellet center to the pellet surface. Dislocation density was highest in the cooler regions of the fuel pellet, with the outer edge experiencing grain refinement and high defect concentrations consistent with the rim structure. The results of the paper highlight the variable dislocation behavior as a function of radial position in high burnup MOX fuels, as well as describe the largely unexplored change in crystal structure of the oxide solid fission product phase.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Radioactive element chemistry and processing

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References (41)

Show source-provided references
1. Status of advanced fuel candidates for sodium fast reactor within the generation IV international forum10.1016/j.jnucmat.2012.09.036 ↗
2. Thermal properties of irradiated UO2 and MOX10.1016/B978-0-08-056033-5.00038-0 ↗
3. Effects of edge dislocations on thermal transport in UO210.1016/j.jnucmat.2012.11.043 ↗
4. Multiscale modeling of thermal conductivity of high burnup structures in UO 2 fuels10.1016/j.jnucmat.2015.12.028 ↗
5. Effects of intergranular gas bubbles on thermal conductivity10.1016/j.jnucmat.2012.06.027 ↗
6. Using coupled mesoscale experiments and simulations to investigate high burn-up oxide fuel thermal conductivity10.1007/s11837-014-1160-3 ↗
7. Thermophysical properties of Mo–Ru–Rh–Pd alloys10.1016/S0925-8388(02)01211-2 ↗
8. The solubility of selected fission products in UO2 and (U, Pu)O210.1016/0022-3115(93)90236-R ↗
9. Thermal properties of SrCeO310.1016/S0925-8388(02)01133-7 ↗
10. Thermochemical and thermophysical properties of alkaline-earth perovskites10.1016/j.jnucmat.2005.04.017 ↗
11. Heat capacities and thermal conductivities of perovskite type BaZrO3 and BaCeO310.1016/S0925-8388(03)00137-3 ↗
12. Thermophysical properties of BaUO< sub> 310.1016/S0022-3115(01)00474-3 ↗
13. Thermophysical properties of BaZrO3 and BaCeO310.1016/S0925-8388(03)00214-7 ↗
14. A liquid-metal reactor core demonstration experiment using HT-910.13182/NT93-A17034 ↗
15. Irradiation performance of fast reactor MOX fuel pins with ferritic/martensitic cladding irradiated to high burnups10.1016/j.jnucmat.2011.02.052 ↗
16. Microstructural characterization of high burn-up mixed oxide fast reactor fuel10.1016/j.jnucmat.2013.05.067 ↗
17. Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel10.1016/j.jnucmat.2013.09.035 ↗
18. Fission product behaviour in phenix fuel pins at high burnup10.1016/0022-3115(92)90453-R ↗
19. Change of fuel-to-cladding gap width with the burn-up in FBR MOX fuel irradiated to high burn-up10.1016/j.jnucmat.2004.01.003 ↗
20. Fuel performance of fast spectrum oxide fuel
21. Oxide fuels
22. Characterization of solid fission products in 13.7% FIMA MOX fuel using electron microscopy techniques10.1016/j.jnucmat.2019.06.042 ↗
23. Plastic deformation in nonstoichiometric UO2 + x single crystals—II. Deformation at high temperatures10.1016/0001-6160(88)90161-7 ↗
24. Full characterization of dislocations in ion-irradiated polycrystalline UO210.1016/j.jnucmat.2017.07.043 ↗
25. Evolution of porosity in the high-burnup fuel structure10.1016/j.jnucmat.2006.09.016 ↗
26. The high burn-up structure in nuclear fuel10.1016/S1369-7021(10)70221-2 ↗
27. Detailed characterisations of high burn-up structures in oxide fuels10.1016/j.jnucmat.2007.04.037 ↗
28. Behavior of fission products zirconium and barium in fast reactor fuel irradiated to high burnup10.1080/18811248.1999.9726267 ↗
29. Phase study on solid fission products, Ba , Sr and Zr in oxide fuel10.1016/0022-3115(74)90118-4 ↗
30. Solid fission product behavior in uranium-plutonium oxide fuel irradiated in a fast neutron flux10.1016/0022-3115(69)90124-X ↗
31. The stability of fission products in uranium dioxide
32. Metallic fission-product inclusions in irradiated oxide fuels10.1016/0022-3115(68)90045-7 ↗
33. Microanalysis of inclusions in irradiated UO210.1016/0022-3115(67)90106-7 ↗
34. The chemical state of the fission products in oxide fuels10.1016/0022-3115(85)90460-X ↗
35. The chemical state of fission products in oxide fuels at different stages of the nuclear fuel cylcle10.13182/NT88-A34065 ↗
36. High temperature investigation of the solid/liquid transition in the PuO2-UO2-ZrO2 system10.1016/j.jnucmat.2015.10.007 ↗
37. A metallographic and X-ray study of the UO2-ZrO2 system10.1016/0022-3115(63)90166-1 ↗
38. Assessment of solid/liquid equilibria in the (U, Zr)O2+y system10.1016/j.jnucmat.2017.07.045 ↗
39. Radial microstructural evolution in low burnup fast reactor MOX fuel10.1016/j.jnucmat.2019.06.009 ↗
40. EBSD and TEM characterization of high burn-up mixed oxide fuel10.1016/j.jnucmat.2013.10.037 ↗
41. Glide mobility of the 1/2[1 1 0](0 0 1) edge dislocation in UO2 from molecular dynamics simulation10.1016/j.ijplas.2016.11.004 ↗