Homogenization-based irradiation performance analysis of U-Mo/Al dispersion fuel plates
Bibliographic record
Abstract
No abstract is available for this record. The assistant can identify its topic from the title, but cannot infer the study’s results.
Source: Not provided · Quality: missing
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · High Temperature Alloys and Creep
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (48)
Show source-provided references
1. Rest · 1995
2. DART model for irradiation-induced swelling of uranium silicide dispersion fuel elements10.13182/NT99-A2960 ↗
3. DART analysis of irradiation behavior of U-Mo/Al dispersion fuels10.13182/NT14-56 ↗
4. Integrated simulation of U-10Mo monolithic fuel swelling behavior10.1016/j.jnucmat.2023.154542 ↗
5. Mechanical behaviors of the dispersion nuclear fuel plates induced by fuel particle swelling and thermal effect II: effects of variations of the fuel particle diameters10.1016/j.jnucmat.2009.12.012 ↗
6. Coulson · 2013
7. A microstructural model of the thermal conductivity of dispersion type fuels with A Fuel matrix interaction layer10.5516/NET.07.2013.714 ↗
8. Thermal conductivity of U–Mo/Al dispersion fuel: effects of particle shape and size, stereography, and heat generation: special issue for ANFC201410.1080/00223131.2015.1021285 ↗
9. The modeling and simulation of the thermal conductivity of irradiated U-Mo dispersion fuel: estimation of the thermal conductivity of the interaction layer10.1016/j.jnucmat.2018.08.014 ↗
10. Hayes · 2002
11. Marelle · 2008
12. Thermal-mechanical coupling behavior analysis on metal-matrix dispersed plate-type fuel10.1016/j.pnucene.2016.11.007 ↗
13. Development of PRIME for irradiation performance analysis of U-Mo/Al dispersion fuel10.1016/j.jnucmat.2018.02.028 ↗
14. MOOSE: a parallel N computational framework for coupled systems of nonlinear equations10.1016/j.nucengdes.2009.05.021 ↗
15. Rest · 2006
16. Jeong · 2025
17. Ye · 2013
18. Thermophysical properties of aluminum 1060 fabricated by equal channel angular pressing10.1007/s10765-012-1176-2 ↗
19. Mechanical analysis of UMo/Al dispersion fuel10.1016/j.jnucmat.2015.07.033 ↗
20. Fission induced swelling of U–Mo/Al dispersion fuel10.1016/j.jnucmat.2015.06.006 ↗
21. ASM Material Data Sheet, (n.d.). https://asm.matweb.com/search/specificmaterial.asp?bassnum=ma6061t6 (accessed April 13, 2025).
22. A modelling study of the inter-diffusion layer formation in U-Mo/Al dispersion fuel plates at high power10.1016/j.jnucmat.2017.11.035 ↗
23. Thermophysical properties of heat-treated U-7Mo/Al dispersion fuel10.1016/j.jnucmat.2018.01.027 ↗
24. Thermal conductivity measurement of the interaction layer between UMo and Al produced by high-energy heavy ion irradiation10.1016/j.jnucmat.2020.152262 ↗
25. A model to predict thermal conductivity of irradiated U–Mo dispersion fuel10.1016/j.jnucmat.2016.01.012 ↗
26. First-principles study of structural, elastic, electronic, vibrational and thermodynamic properties of uranium aluminides10.1016/j.commatsci.2018.11.008 ↗
27. Evaluation of properties and FEM model of the friction welded mild steel-Al6061-alumina10.1590/S1516-14392012005000178 ↗
28. Thermal expansion of Al U and Al U Zr alloys10.1016/0022-3115(95)00090-9 ↗
29. 3.14 - Uranium intermetallic fuels (U–Al, U–Si, U–Mo)
30. K. Farrell, R.T. King, Tensile properties of neutron-irradiated 6061 aluminum alloy in annealed and precipitation-hardened conditions, (n.d.). https://asmedigitalcollection.asme.org/astm-ebooks/book/1312/chapter/27793313/Tensile-Properties-of-Neutron-Irradiated-6061 (accessed April 13, 2025).
31. Modeling of interaction layer growth between U-Mo particles and an al matrix10.5516/NET.07.2013.713 ↗
32. Oxidation of aluminum alloy cladding for research and test reactor fuel10.1016/j.jnucmat.2008.06.032 ↗
33. Computer simulation of close random packing of equal spheres10.1103/PhysRevA.32.2347 ↗
34. OpenMC: a state-of-the-art Monte Carlo code for research and development10.1016/j.anucene.2014.07.048 ↗
35. L. Olivares, J. Marin, M. Barrera, C. Gutierrez, J. Lisboa, Dispersed type fuel miniplates based UMo alloy powders atomized; Miniplacas combustibles tipo disperso en base a polvos atomizados de aleacion de UMo, (2012). https://www.osti.gov/etdeweb/biblio/22035307 (accessed April 13, 2025).
36. Irradiation-enhanced interdiffusion in the diffusion zone of U-Mo dispersion fuel in Al10.1007/BF02736563 ↗
37. Effective elastic properties of additively manufactured metallic cellular structures using numerical unit-cell homogenization10.1007/s40964-020-00141-7 ↗
38. Post-irradiation examination of uranium–7wt% molybdenum atomized dispersion fuel10.1016/j.jnucmat.2004.07.004 ↗
39. Analytical local stress model for UMo/Al dispersion fuel10.1016/j.jnucmat.2019.151881 ↗
40. Thermal conductivity modeling of U-Mo/Al dispersion fuel10.1016/j.jnucmat.2015.08.051 ↗
41. Effect of heat treatment on thermal conductivity of U-Mo/Al alloy dispersion fuel10.1023/A:1026159303485 ↗
42. Thermophysical properties of U–Mo/Al alloy dispersion fuel meats10.1007/s10765-007-0212-0 ↗
43. Thermal properties of U-7Mo/Al dispersion fuel10.1016/j.jnucmat.2017.09.039 ↗
44. Effects of irradiation on the microstructure of U–7Mo dispersion fuel with Al–2Si matrix10.1016/j.jnucmat.2012.01.013 ↗
45. 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 ↗
46. Post-irradiation analysis of U-Mo miniplates tested to date
47. Assessment of thermal–hydraulic correlations for narrow rectangular channels with high heat flux and coolant velocity10.1016/j.ijheatmasstransfer.2016.03.099 ↗
48. Effect of stress evolution on microstructural behavior in U-Mo/Al dispersion fuel10.1016/j.jnucmat.2017.02.023 ↗