Nanoindentation testing of high burn-up fast reactor mixed oxide fuel
Source abstract
Abstract
Continued research into the mechanical properties of nuclear fuel is necessary to improve modeling of the pellet-cladding mechanical interactions that occur in nuclear reactors during operation. Small scale mechanical testing with focused ion beam equipment can provide a means to study the mechanical properties of irradiated nuclear fuels by measuring their mechanical properties on minute volumes of material. In this work, room temperature nanoindentation measured the hardness and Young`s modulus of fast reactor mixed oxide (MOX) fuel irradiated to 183 GWd/tHM. The hardness of the MOX fuel had a measured value of 11.2 ± 0.4 GPa. The Young`s modulus of the MOX fuel had a value of 158 ± 6 GPa. The measured hardness and Young`s modulus are discussed in the context of the available literature data. In addition, pathways toward elevated temperature testing and other mechanical properties are proposed.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (32)
Show source-provided references
1. Room-temperature microindentation behaviour of LWR-fuels, part 1: fuel microhardness10.1016/S0022-3115(03)00328-3 ↗
2. Cappia · 2017
3. Microhardness and Young's modulus of high burn-up UO2 fuel10.1016/j.jnucmat.2016.07.015 ↗
4. Advancements in the behavioral modeling of fuel elements and related structures10.1016/0029-5493(92)90005-G ↗
5. Determination of high burn-up nuclear fuel elastic properties with acoustic microscopy10.1016/j.jnucmat.2011.09.010 ↗
6. Physical and mechanical characterization of irradiated uranium dioxide with a broad burnup range and different dopants using acoustic microscopy10.1016/j.jnucmat.2017.07.041 ↗
7. Young's modulus evaluation of high burnup structure in UO2 with nanometer resolution10.1016/j.jnucmat.2018.04.004 ↗
8. Scanning acoustic microscope for mechanical characterization and density estimation of irradiated nuclear fuel10.1016/j.pnucene.2013.07.018 ↗
9. Small-scale mechanical testing on nuclear materials: bridging the experimental length-scale gap10.1016/j.scriptamat.2017.04.026 ↗
10. Plasticity of UO2 studied and quantified via elevated temperature micro compression testing10.1016/j.jnucmat.2019.07.022 ↗
11. Nano- and micro-indentation testing of sintered UO2 fuel pellets with controlled microstructure and stoichiometry10.1016/j.jnucmat.2019.01.021 ↗
12. Thermophysical and mechanical property assessment of UB2 and UB4 sintered via spark plasma sintering10.1016/j.jallcom.2019.153216 ↗
13. D. Frazer, D. Jadernas, N. Bolender, J. Madden, J. Giglio, P. Hosemann “Elevated temperature microcantilever testing of fresh U-10Mo Fuel” 526 (2019) 15174610.1016/j.jnucmat.2019.151746 ↗
14. Mechanical properties examined by nanoindentation for selected phases relevant to the development of monolithic uranium-molybdenum metallic fuels10.1016/j.jnucmat.2017.02.018 ↗
15. Mechanical properties of UO2 thin films under heavy ion irradiation using nanoindentation and finite element modeling” J10.1016/j.jnucmat.2016.07.047 ↗
16. Nanoindentation studies of UO2 and (U,Ce)O210.1016/j.jallcom.2004.03.084 ↗
17. Grain boundary and lattice frature toughness of UO2 measured using small-scale mechanics10.1007/s11837-020-04118-3 ↗
18. In-situ transmission electron microscopy microcantilever and nanoindentation testing of UO210.1007/s11837-020-04102-x ↗
19. Irradiation effects on the fracture properties of UO2 fuels studies by micro-mechanical testing
20. Fracture properties of an irradiated PWR UO2 fuel evaluated using micro-cantilever bending testing10.1016/j.jnucmat.2020.152209 ↗
21. Lancaster · 1992
22. M. Teague, Post irradiation examination of legacy FFTF oxide fuel, 2012.
23. The chemical state of fission products in oxide fuels at different stages of the nuclear fuel cycle10.13182/NT88-A34065 ↗
24. Nanoindentation in materials research: past, present, and future10.1557/mrs2010.717 ↗
25. The elastic constants of polycrystalline UO2 and (U,Pu) mixed oxides: a review and recommendations
26. L. Bates HW-SA-3014 [1963]1/18;CONF-50-16 [1963]; Am. Ceram. Soc. 65th Ann. Meeting, Pittsburgm Pa., 1963 Paper 2-2s-63; N.S.A 17 [1963]No. 34323; Am. Ceram. Sc. Bull 42 (1963) 265
27. Hosemann “small-scale mechanical testing of UO2
28. Elevated temperature nanoindentation testing of UO2
29. High temperature mechancial properties of fluorite cyrstal structured materials (CeO2, ThO2, and UO2) and advanced accident tolerant fuels (U3Si2, UN, and UB2)10.1016/j.jnucmat.2021.153035 ↗
30. Evolution of spent nuclear fuel in dry storage conditions for millennia and beyond10.1016/j.jnucmat.2014.03.055 ↗
31. Room-temperature microindentation behavior of LWR-fuels, part 1: fuel microhardness10.1016/S0022-3115(03)00328-3 ↗
32. Post-irradiation examinations of annular mixed oxide fuels with average burnup 4 and 5 % FIMA10.1016/j.jnucmat.2020.152076 ↗