Corrosion behavior of high uranium density fuels
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 (58)
Show source-provided references
1. P.B. Lyons, Development of Light Water Reactor Fuels with Enhanced Accident Tolerance, Report to Vongress, Washington, DC, 2015.
2. R. Rebak, W. Gassmann, K. Terrani, Managing Nuclear Power Plant Safety With FeCrAl Alloy Fuel Cladding, Top Safe (2017).10.1557/adv.2017.5 ↗
3. Accident tolerant fuel cladding development: promise, status, and challenges10.1016/j.jnucmat.2017.12.043 ↗
4. Enchanced high-temperature performances of SiC/SiC composites by high densification and crystalline structure10.1016/j.compscitech.2010.11.026 ↗
5. Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings
6. Paralinear oxidation of CVD SiC in water vapor10.1111/j.1151-2916.1997.tb02810.x ↗
7. High-temperature tensile strength of near-stoichiometric SiC/SiC composites10.1016/S0022-3115(02)01049-8 ↗
8. Vacuum-arc chromium-based coatings for protection of zirconium alloys from the high-temperature oxidation in air10.1016/j.jnucmat.2015.06.016 ↗
9. Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating10.1016/j.jnucmat.2015.06.030 ↗
10. Investigation of the impact of coatings on corrosion and hydrogen uptake of Zircaloy-410.1016/j.jnucmat.2015.09.041 ↗
11. K. Sakamoto, A. Ouchi, A. Suzuki, T. Higuchi, M. Hirai, N. Oono, S. UkaiDevelopment of Ce-type FeCrAl-ODS ferritic steel to accident tolerant fuel for BWRs, Fuel 2016: LWR Fuels with Enhanced Safety and Performance.2016, 2016673680.
12. Accident-Tolerant Fuel☆
13. Performance and properties evolution of near-term accident tolerant fuel: Cr-doped UO210.1016/j.jnucmat.2024.155022 ↗
14. Raman spectroscopy coupled to principal component analysis for studying UO2 nuclear fuels with different grain sizes due to the chromia addition10.1016/j.jnucmat.2020.152581 ↗
15. Impact of dopants and leachants on modern UO2-based fuels alteration under final storage conditions: single and joint effects10.1016/j.jnucmat.2025.155635 ↗
16. T.M. Crede, Y. Long, M.P. Joshnson, M.A. Shockling, Jakub, R.M., B. Andersson, J.J. Klingensmith, G.A. Jewett, A.M. DiLullo, Y. Sung, H. Lam, U. Bachrach, J. Wright, M. Puide, P. Khambatta, Westinghouse Advanced Doped Pellet Technology (ADOPTTM) Fuel, 2022.
17. Advanced doped UO2 pellets in LWR applications10.1080/18811248.2006.9711184 ↗
18. Burnable absorbers in nuclear reactors - a review
19. Increasing efficiency of nuclear fuel using burnable absorbers10.1016/j.pnucene.2019.103077 ↗
20. A. van Veelen, S. Bang, J.T. White, Characterization and Performance of Advanced Dopants for HBU and ATF, Los Alamos National Laboratory, 2024.
21. Factors governing microstructure development of Cr2O3-doped UO2 during sintering10.1016/S0022-3115(01)00626-2 ↗
22. Chromia doped UO2 fuel: investigation of the lattice parameter10.1016/j.jnucmat.2012.02.025 ↗
23. Oxidation of accident tolerant fuels models based on Cr-doped UO2 for the safety of nuclear storage facilities10.1016/j.jnucmat.2023.154502 ↗
24. Fission gas diffusion and release for Cr2O3-doped UO2: from the atomic to the engineering scale10.1016/j.jnucmat.2020.152590 ↗
25. Metrics for the technical performance evaluation of light water reactor accident-Tolerant fuel10.13182/NT15-149 ↗
26. A.T. Nelson, Property and Performance Assessment to Support Candidacy of U3Si2 as LWR fuel, Los Alamos National Lab.(LANL), Los Alamos, NM (United States), 2018.
27. 7.05 - thermodynamic and thermophysical properties of the actinide nitrides
28. Challenges and opportunities to alloyed and composite fuel architectures to mitigate high uranium density fuel oxidation: Uranium mononitride10.1016/j.jnucmat.2021.153048 ↗
29. Thermophysical properties of U3Si2 to 1773 K10.1016/j.jnucmat.2015.04.031 ↗
30. Spark plasma sintering (SPS) densified U3Si2 pellets: microstructure control and enhanced mechanical and oxidation properties10.1016/j.jallcom.2020.154022 ↗
31. Degradation of UN and UN–U3Si2 pellets in steam environment10.1080/00223131.2016.1274689 ↗
32. U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels10.1016/j.jnucmat.2020.152147 ↗
33. Aluminum-doped U3Si2 composite fuels with enhanced oxidation resistance10.1016/j.jallcom.2020.157319 ↗
34. Cr-doped U3Si2 composite fuels under steam corrosion10.1016/j.corsci.2020.109001 ↗
35. Oxidation kinetics of SPS-densified U3Si2 fuels—Microstructure impact10.1063/5.0086630 ↗
36. High-temperature compressive creep tests of U3Si2 with spark plasma sintering: experiments and finite element modeling10.1016/j.jnucmat.2022.153568 ↗
37. Fabrication and thermophysical property characterization of UN/U3Si2 composite fuel forms10.1016/j.jnucmat.2017.08.041 ↗
38. Uranium nitride (UN) pellets with controllable microstructure and phase–fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties10.1016/j.jnucmat.2021.153272 ↗
39. Uranium mononitride: heat capacity and thermal conductivity from 298 to 1000 K10.1016/0022-3115(71)90059-6 ↗
40. Oxidation kinetics of SPS-densified U3Si2 fuels—microstructure impact10.1063/5.0086630 ↗
41. UN and U3Si2 composites densified by spark plasma sintering for accident-tolerant fuels10.1016/j.ceramint.2021.12.292 ↗
42. Cr-incorporated uranium nitride composite fuels with enhanced mechanical performance and oxidation resistance10.1016/j.jnucmat.2021.153486 ↗
43. Steam oxidation of uranium mononitride in pure and reducing steam atmospheres to 1200° C10.1016/j.jnucmat.2021.153487 ↗
44. Thermal expansion and steam oxidation of uranium mononitride analysed via in situ neutron diffraction10.1016/j.jnucmat.2022.154215 ↗
45. Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation10.1016/j.jnucmat.2015.06.027 ↗
46. 3Y-TZP Toughened and Oxidation-resistant U3Si2 Composites for Accident Tolerant Fuels10.1016/j.jnucmat.2020.152691 ↗
47. Uranium nitride (UN) pellets with controllable microstructure and phase – fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties10.1016/j.jnucmat.2021.153272 ↗
48. Hydrolysis of uranium mononitride10.1039/tf9676301286 ↗
49. Grain growth in uranium nitride prepared by spark plasma sintering10.1016/j.jnucmat.2018.02.041 ↗
50. Oxidation of U3Si2: the role of exothermic energy10.1016/j.jnucmat.2022.153874 ↗
51. High temperature steam oxidation dynamics of U3Si2 with alloying additions: Al, Cr, and Y10.1016/j.jnucmat.2020.152072 ↗
52. Radiation induced dissolution of U3Si2 - a potential accident tolerant fuel10.1016/j.jnucmat.2019.01.023 ↗
53. Uranium nitride stability in aqueous solutions under anoxic and oxidizing conditions – expected behaviour under repository conditions in comparison to alternative nuclear fuel materials10.1016/j.jnucmat.2023.154334 ↗
54. The effects of hydrogen absorption in U3Si5 and its thermodynamic properties10.1016/j.jnucmat.2023.154872 ↗
55. Accurate lattice parameter measurements of stoichiometric uranium dioxide10.1016/j.jnucmat.2015.01.029 ↗
56. Refinement of the alpha-U4O9 crystalline structure: new insight into the U4O9-> U3O810.1021/ic200316b ↗
57. Low-temperature oxidation of fine UO2 Powders: a process of nanosized domain development10.1021/acs.inorgchem.6b00127 ↗
58. Energetics of oxidation and formation of uranium mononitride10.1016/j.jnucmat.2022.153904 ↗