journal article·2026-05Open access

On the performance of metallic coating barriers in U-Mo/Al fuels: A quantitative evaluation of Al/X/U-Mo trilayer structures (X = Mo, Zr, or W) under heavy ion irradiation

Jingyi Shi, Anna Oberbauer, Christian Schwarz, Eric Fuchs, Florian Troll, Tobias Chemnitz, Winfried Petry

Abstract

This study evaluates the effectiveness of molybdenum (Mo), zirconium (Zr), and tungsten (W) coatings as diffusion barriers in U-Mo/Al fuel systems, aiming to suppress interdiffusion between U-Mo and Al, a process that significantly degrades fuel performance. Well-defined Al/X/U-Mo trilayer structures (X = Mo, Zr, or W) with coating thicknesses ranging from 50 nm to 5 µm were subjected to heavy ion irradiation with iodine or xenon ions up to 7 × 10 17 ions/cm 2 , simulating fission product damage under varied irradiation conditions. Cross-sectional scanning electron microscopy (SEM) and energy-dispersive X-ray spectroscopy (EDS) analyses revealed distinct performance trends: Mo coatings underwent rapid consumption and formed Al-Mo intermixing layers that promoted continued U-Mo-Al interdiffusion, indicating poor long-term stability. Zr coatings exhibited thickness-dependent behavior, with thin layers fully consumed while thicker coatings provided notable resistance. W coatings with thicknesses ≥ 1 µm showed the highest stability, effectively suppressing interdiffusion under the tested conditions, consistent with the less thermodynamically favorable formation of Al-W compounds. These findings provide quantitative guidance for selecting robust diffusion barriers in advanced U-Mo/Al fuel architectures and help explain mechanisms observed in in-pile irradiation experiments.
Source: openalex_inverted_index · Quality: baseline

Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (32)

Show source-provided references
1. Post-irradiation examination of uranium-7wt% molybdenum atomized dispersion fuel10.1016/j.jnucmat.2004.07.004 ↗
2. Transmission electron microscopy investigation of irradiated U-7wt%Mo dispersion fuel10.1016/j.jnucmat.2007.12.006 ↗
3. Post-irradiation analysis of low enriched U-Mo/Al dispersion fuel miniplate tests, RERTR 4 & 5
4. Wachs · 2007
5. Irradiation behavior of the interaction product of U-Mo fuel particle dispersion in an Al matrix10.1016/j.jnucmat.2011.07.032 ↗
6. TEM analysis of irradiation-induced interaction layers in coated UMo/X/Al trilayer systems (X= Ti, Nb, Zr, and Mo)10.1016/j.jnucmat.2017.12.015 ↗
7. Effectiveness of the metal coating on U-7Mo dispersion fuel in Al during irradiation10.1016/j.jnucmat.2019.151945 ↗
8. Microstructure evolution and phase transformation of heavy-ion irradiated U-Mo/Al fuels10.1016/j.jnucmat.2020.152399 ↗
9. Quantitative comparability of heavy ion and in-pile irradiations on UMo fuel systems10.1016/j.jnucmat.2018.04.007 ↗
10. U(Mo) grain refinement induced by irradiation with high energy iodine10.1016/j.jnucmat.2021.152850 ↗
11. Temperature measurements during high flux ion beam irradiations10.1063/1.4941720 ↗
12. J. Shi, Qualification of U-Mo fuel for research reactors: characterisation of the interfaces between U-Mo kernel, diffusion barrier and Al matrix under heavy ion irradiation, 2021. PhD thesis, Technical University of Munich.
13. Smidt · 1976
14. Fuel plate temperatures during operation of FRM II
15. J.F. Ziegler, SRIM—The stopping and range of ions in matter, 2013. http://www.srim.org/.
16. A simple model for alloys. I. Rules for the alloying behaviour of transition metals
17. Miedema calculator: a thermodynamic platform for predicting formation enthalpies of alloys within framework of Miedema’s theory10.1016/j.cpc.2016.08.013 ↗
18. SEMPER FIDELIS – PIE progress
19. Swelling of U(Mo)-Al(Si) dispersion fuel under irradiation - non-destructive analyses of the LEONIDAS E-FUTURE plates10.1016/j.jnucmat.2012.06.045 ↗
20. Effect of fission rate on the microstructure of coated UMo dispersion fuel10.1016/j.jnucmat.2017.06.036 ↗
21. A. Leenaers, Surface-engineered low-enriched uranium-molybdenum fuel for research reactors, 2014. PhD thesis, University of Ghent.
22. Temperature effects on interdiffusion of al and U-Mo under irradiation10.1016/j.jnucmat.2020.152684 ↗
23. C. Schwarz, Towards FRM II LEU conversion: viable barriers to prevent excessive radiation-induced interdiffusion in monolithic U-Mo fuel plates, 2023. PhD thesis, Technical University of Munich.
24. Preliminary Report on U-Mo Monolithic Fuel for Research Reactors
25. RERTR-12 Insertion 1 Irradiation Summary Report
26. RERTR-12 Insertion 2 Irradiation Summary Report
27. RERTR-12 Post-irradiation Examination Summary Report
28. AFIP-6 Irradiation Summary Report
29. Microstructurally validated stable and predictable swelling in low-enriched uranium monolithic U-10Mo fuel mini-plates10.1016/j.jnucmat.2025.155746 ↗
30. Innovation and qualification of LEU research reactor fuels and materials10.1051/epjn/2022051 ↗
31. Mughabghab · 2018
32. Materials selection for nuclear applications: challenges and opportunities10.1016/j.scriptamat.2017.04.027 ↗