journal article·2024-11Open access

Formation of uranium nitride nanoparticles via mechanical alloying of uranium-molybdenum alloy fuels in gaseous nitrogen

James Zillinger, Nathan Jerred, Mukesh Bachhav, Adrian R. Wagner, Tiankai Yao, Rabi Khanal, Samrat Choudhury, Indrajit Charit

Abstract

Uranium-molybdenum (U-Mo) alloys show promise as a nuclear fuel system due to their high thermal conductivity and fuel loading capability. However, U-Mo systems are susceptible to irradiation induced swelling ultimately affecting the cladding via mechanical and chemical interactions. To address these shortcomings, this research investigated the formation of uranium mononitride (UN) nanoparticles within a 90 wt% U/ 10 wt% Mo (U-10Mo) matrix to act as a prospective defect sink for fission products at nanometric hetero-interfaces. To promote the formation of UN, U-10Mo powders were mechanically alloyed under a high purity nitrogen atmosphere. Variations of the milling process investigated included media size, duration of milling, and number of times the milling jar was re-aerated with nitrogen gas. Characterization of the fuel microstructure was completed using light element analysis, X-ray diffraction, scanning and transmission-electron microscopy, electron energy loss spectroscopy, and atom probe tomography. UN nanoparticles measuring 1–5 nm in radius were observed in the U-Mo matrix as early as 1 h into the mechanical alloying process. Milling time in excess of 10 h was found to lead to deleterious effects induced by the stainless-steel milling media.
Source: expertdata · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Radioactive element chemistry and processing · Fusion materials and technologies

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

References (50)

Show source-provided references
1. J. Rest and Y.S.H. Kim, G.L. Meyer, M.K. Hayes, S.L.A.N. Laboratory. (2006). U-Mo Fuels Handbook.
2. U–Mo alloy fuel for TRU-burning advanced fast reactors10.1016/j.jnucmat.2013.01.324 ↗
3. Material Properties of Unirradiated Uranium-Molybdenum (U-Mo) Fuel for Research Reactors
4. Ahmann · 1945 · 28
5. 3.14 - Uranium Intermetallic Fuels (U–Al, U–Si, U–Mo)
6. Fission product induced swelling of U–Mo alloy fuel10.1016/j.jnucmat.2011.08.018 ↗
7. Metallic fast reactor fuels10.1016/0149-1970(96)00005-4 ↗
8. Nuclear Metal Fuel: Characteristics, Design, Manufcaturing, Testing and Operating History
9. Fission Gas Behaviors and Relevant Phenomena in Different Nuclear Fuels: A Review of Models and Experiments," (in English)
10. Recent trends in metallic fast reactor fuels research10.1016/j.jnucmat.2021.153377 ↗
11. Swelling of U-Mo Monolithic Fuel: Developing a Predictive Swelling Correlation under Research Reactor Conditions10.1016/j.jnucmat.2020.152703 ↗
12. 5.01 - Metal Fuel☆
13. 3.23 - Metal Fuel Performance Modeling and Simulation
14. Constituent redistribution in U-Pu-Zr fuel during irradiation10.1016/j.jnucmat.2004.01.012 ↗
15. Fuel cladding chemical interaction in metallic sodium fast reactor fuels: A historical perspective10.1016/j.jnucmat.2018.09.045 ↗
16. Development of advanced ultra-high burnup SFR metallic fuel concept - Project overview
17. Experimental assessment of antimony (Sb) in pure uranium for immobilizing fission product lanthanides10.1016/j.jnucmat.2020.152135 ↗
18. Microstructure and diffusion behavior of uranium fuel with minor additives10.1016/j.jnucmat.2020.152200 ↗
19. Interactions and immobilization of lanthanides with dopants in uranium-based metallic fuels10.1016/j.jnucmat.2020.152372 ↗
20. A novel approach to selection of dopant to immobilize neodymium in uranium-based metallic fuels10.1016/j.jnucmat.2019.151922 ↗
21. Evaluation of Tellurium as a Fuel Additive in Neodymium-Containing U-Zr Metallic Fuel10.1038/s41598-019-51852-z ↗
22. Diffusion behavior of lanthanide-additive compounds (Ce4Sb3, Ce2Sb, and CeTe) against HT9 and Fe10.1016/j.matchar.2019.02.012 ↗
23. Assessment of Te as a U-Zr fuel additive to mitigate fuel-cladding chemical interactions10.1016/j.jnucmat.2018.10.050 ↗
24. Lanthanides in metallic nuclear fuels: Their behavior and methods for their control10.1016/j.jnucmat.2011.08.036 ↗
25. History and Outlook of ODS/NFA Ferritic Alloys for Nuclear Applications
26. Formation of titanium and zirconium nitrides by mechanical alloying10.1063/1.106285 ↗
27. Development of austenitic nanostructures in high-nitrogen steel powders processed by mechanical alloying," (in English)10.1007/s11661-002-0045-1 ↗
28. Processing of Oxide Dispersion Strengthened Alloys via Mechanical Alloying and Spark Plasma Sintering
29. Non-uniform Solute Segregation at Semi-Coherent Metal/Oxide Interfaces10.1038/srep13086 ↗
30. Massive Interfacial Reconstruction at Misfit Dislocations in Metal/Oxide Interfaces10.1038/srep06533 ↗
31. N.I.H. o. Fame. "NIHF Inductee Alfred Y. Cho Invented Molecular Beam Epitaxy." https://www.invent.org/inductees/alfred-y-cho (accessed 7/31/2023, 2023).
32. The Open Quantum Materials Database (OQMD): assessing the accuracy of DFT formation energies10.1038/npjcompumats.2015.10 ↗
33. Materials Design and Discovery with High-Throughput Density Functional Theory: The Open Quantum Materials Database (OQMD)10.1007/s11837-013-0755-4 ↗
34. Material property correlations for uranium mononitride: IV. Thermodynamic properties10.1016/0022-3115(90)90377-Y ↗
35. Synthesis of uranium nitride by a mechanically induced gas-solid reaction10.1016/j.jnucmat.2008.07.043 ↗
36. Templated growth of complex nitride island dispersions by controlled internal reactions," (in English)
37. D. Banerjee, "X-Ray Diffraction (XRD)," ed. Department of Chemical Engineering: IIT Kanpur.
38. Amorphization reaction during mechanical alloying: influence of the milling conditions10.1007/BF00576540 ↗
39. Recrystallization kinetics of cold-rolled U-10wt% Mo10.1016/j.jnucmat.2018.10.046 ↗
40. Comparison of Nanoscaled and Bulk NiO Structural and Environmental Characteristics by XRD, XAFS, and XPS10.1021/cm300739y ↗
41. The Scherrer Formula for X-Ray Particle Size Determination10.1103/PhysRev.56.978 ↗
42. The chemical thermodynamic properties of nuclear materials I. Uranium mononitride10.1016/0021-9614(72)90057-2 ↗
43. Determination of Gray Cast Iron Age Strengthening by Nondestructive Methods: Effect of Alloying Elements10.1007/s11665-019-04180-2 ↗
44. Thermodynamic assessment of the Fe-U binary system10.1361/105497103770330730 ↗
45. R.L. Ludwig, "Effect of small additions of silicon, iron, and aluminum on the room-temperature tensile properties of high-purity uranium," United States, 1983-11-14 1983. [Online]. Available: https://www.osti.gov/biblio/5581747 https://www.osti.gov/servlets/purl/5581747.10.2172/5581747 ↗
46. Effect of iron on the hot cracking of uranium weld metal Part I
47. Irradiation behavior of low-enriched U6Fe-Ai dispersion fuel elements10.1016/0022-3115(87)90079-1 ↗
48. The interaction of iron with molten uranium10.1016/0022-3115(66)90044-4 ↗
49. Cr-rich structure evolution and enhanced mechanical properties of CoCrFeNi high entropy alloys by mechanical alloying10.1016/j.jmrt.2024.03.116 ↗
50. Microstructure and mechanical properties of mechanically-alloyed CoCrFeNi high-entropy alloys using low ball-to-powder ratio10.1016/j.jallcom.2022.168196 ↗