Anisotropic lattice thermal expansion of uranium-based metallic fuels: A high-temperature X-ray diffraction study
Source abstract
Abstract
Abstract We characterized the lattice parameter and phase transformation behaviors of six uranium-based metallic fuels in the temperature range 303–1173 K using in situ high-temperature X-ray diffraction (HT-XRD). In all of the fuels, α-U crystal structure almost vanished at 1023 K while UO2 crystal structure started forming at 843 K. Pawley refinement of HT-XRD data revealed anisotropic lattice thermal expansion with increases along the a- and c-axes upon annealing in all the metallic fuels. Furthermore, we confirmed that rare-earth elements (Nd, Ce, Pr, and La) contained in the U–10Zr metallic fuel hardly influenced the thermal behavior of the lattice parameters.
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
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (34)
Show source-provided references
1. Metallic fast reactor fuels10.1016/0149-1970(96)00005-4 ↗
2. Extended fuel swelling models and ultra high burn-up fuel behavior of U–Pu–Zr metallic fuel using FEAST-METAL10.1016/j.nucengdes.2013.02.004 ↗
3. A review of inherent safety characteristics of metal alloy sodium-cooled fast reactor fuel against postulated accidents10.1016/j.net.2015.03.004 ↗
4. Change of composition in metallic fuel slug of U–Zr alloy from high-temperature annealing10.1002/bkcs.10896 ↗
5. Quantitative and isotopic analysis of released and retained krypton and xenon fission gases from irradiated metallic fuels10.1007/s10967-017-5254-6 ↗
6. Crystallographic characterization of irradiated U-10Zr and U-10Zr-5Ce metallic fuels10.1007/s10967-017-5591-5 ↗
7. Development of a new casting method to fabricate U–Zr alloy containing minor actinides10.1007/s10967-013-2767-5 ↗
8. Swelling behavior of U-Pu-Zr fuel10.1007/BF02671924 ↗
9. Studies of the reaction between metal fuels and T91 cladding10.1016/j.jnucmat.2011.02.016 ↗
10. Coexistence of the α and δ phases in an as-cast uranium-rich U–Zr alloy10.1016/j.jnucmat.2013.01.313 ↗
11. Evidence of zirconium nano-agglomeration in as-cast dilute U–Zr alloys10.1016/j.jnucmat.2014.04.040 ↗
12. Microstructural investigation of as-cast uranium rich U–Zr alloys10.1016/j.jnucmat.2016.01.005 ↗
13. Decomposition of the γ phase in as-cast and quenched U–Zr alloys10.1016/j.jnucmat.2016.02.028 ↗
14. Fuel-Cladding chemical interaction in U-Pu-Zr metallic fuels: a critical review10.1080/00295450.2017.1323535 ↗
15. Phase characteristics of rare earth elements in metallic fuel for a sodium-cooled fast reactor by injection casting10.1016/j.jnucmat.2017.01.018 ↗
16. Studying radiotoxic materials by high temperature X-ray diffraction10.1016/j.apmt.2016.03.005 ↗
17. Lattice thermal expansion of Pu1−yAmyO2−x plutonium–americium mixed oxides10.1107/S1600576717014832 ↗
18. Thermophysical properties of matter - the TPRC data series
19. 2.01 - the actinides elements: properties and characteristics
20. An evaluation of the properties of As-cast U-rich U–Zr alloys10.1016/j.jallcom.2009.02.077 ↗
21. Experimentally known properties of U-10Zr alloys: a critical review10.1080/00295450.2018.1435137 ↗
22. Fabrication of uranium alloy fuel slug for sodium-cooled fast reactor by injection casting10.1007/s10967-014-3202-2 ↗
23. Insight into the Am–O phase equilibria: a thermodynamic study coupling high-temperature XRD and CALPHAD modeling10.1021/acs.inorgchem.7b00572 ↗
24. Stable lattice thermal expansion of ZIRLO™: high-temperature X-ray diffraction results10.1016/j.jnucmat.2019.05.046 ↗
25. The immiscibility limits of uranium with the rare-earth metals
26. La-U (Lanthanum-Uranium)10.1361/105497199770340699 ↗
27. Diffusion of cerium in uranium-zirconium solid solutions10.2320/matertrans.44.47 ↗
28. Performance of FCCI barrier foils for U–Zr–X metallic fuel10.1016/j.jnucmat.2009.03.011 ↗
29. Oxidation of U-10 at% Zr alloy in air at 432–1028 K10.1016/0022-3115(94)90235-6 ↗
30. Studies on U-Zr and U-Pu-Zr alloys for determination of Cl and F using pyrohydrolysis10.1515/ract-2013-2203 ↗
31. Zegler · 1962
32. Lattice parameter changes associated with the rim-structure formation in high burn-up UO2 fuels by micro X-ray diffraction10.1016/S0022-3115(00)00236-1 ↗
33. On the oxidation state of UO2 nuclear fuel at a burn-up of around 100 MWd/kgHM10.1016/j.jnucmat.2005.05.010 ↗
34. Lattice contraction in the rim zone as controlled by recrystallization: additional evidence10.1016/j.jnucmat.2007.03.173 ↗