Recent trends in metallic fast reactor fuels research
Source abstract
Abstract
Abstract Metallic nuclear fuels have been extensively investigated for more than 60 years. Early studies noted that metallic fuels exhibit characteristic irradiation behaviors that set them apart from oxide fuels. By performing a critical review of historical data, the current gaps in the understanding of metallic U-Zr and U-Pu-Zr fuels (e.g., constituent redistribution, swelling and fission gas release) and recommendations for future research direction can be identified. This paper reviews and highlights the key aspects of the metallic fuel irradiation behaviors, with respect to the gaps in current understanding, based on the research performed in the past 3 years.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Radioactive element chemistry and processing
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (61)
Show source-provided references
1. A summary of the department of energy’s advanced demonstration and test reactor options study10.1080/00295450.2017.1336029 ↗
2. Metallic fuels for advanced reactors10.1016/j.jnucmat.2009.03.007 ↗
3. Aitkaliyeva · 2020
4. A CALPHAD-informed approach to modeling constituent redistribution in Zr-based metallic fuels using BISON10.1016/j.jnucmat.2020.152657 ↗
5. Fuel Design and Fabrication: Fast-Reactor Metal Fuels10.1016/B978-0-12-819725-7.00067-2 ↗
6. Irradiation Performance: Fast Reactor Fuels10.1016/B978-0-12-819725-7.00182-3 ↗
7. Fuel-Cladding Chemical Interaction in U-Pu-Zr Metallic Fuels: A Critical Review10.1080/00295450.2017.1323535 ↗
8. Fuel cladding chemical itneraction in metallic sodium fast reactor fuels: A historical perspective10.1016/j.jnucmat.2018.09.045 ↗
9. A Critical Review of the Experimentally Known Properties of U-Pu-Zr Alloys. Part 1: Phases and Phase Diagrams10.1080/00295450.2019.1578573 ↗
10. A Critical Review of the Experimentally Known Properties of U-Pu-Zr Alloys. Part 2: Thermal and Mechanical Properties10.1080/00295450.2019.1623617 ↗
11. Zr-Alloyed Metallic Fuel Properties10.1016/B978-0-12-819725-7.00094-5 ↗
12. Postirradiation examination results of several metallic fuel alloys and forms from low burnup AFC irradiations10.1016/j.jnucmat.2018.07.003 ↗
13. Postirradiation examination on metallic fuel in the AFC-2 irradiaiton test series10.1016/j.jnucmat.2018.07.019 ↗
14. Swelling behavior of U-Pu-Zr fuel10.1007/BF02671924 ↗
15. Irradiation performance of nonfertile (Pu-MA-Zr) fast reactor metal fuels10.1016/j.jnucmat.2020.152480 ↗
16. Postirradiation examination of FUTURIX-FTA metallic alloy experiments10.1016/j.jnucmat.2018.12.051 ↗
17. Characterization of minor actinides bearing metallic fuel pin irradiated in EBR-II10.1016/j.jnucmat.2020.152279 ↗
18. Development of a U-19Pu-10Zr fuel performance benchmark case based on the IFR-1 experiment10.1016/j.jnucmat.2021.152997 ↗
19. Microstructure evolution of U-Zr system in a thermal cycling neutron diffraction experiment: extruded U-10Zr (wt. %)10.1016/j.jnucmat.2020.152665 ↗
20. In situ monitoring of microstructure evolution during thermal processing of uranium-zirconium alloys using laser-generated ultrasound10.1016/j.jnucmat.2021.153005 ↗
21. Investigation of the microstructure evolution of alpha uranium after in pile transient10.1016/j.jnucmat.2020.152467 ↗
22. Calculation of Dynamical Phase Diagram in U-Zr Binary System Under Irradiation
23. On spinodal-like phase decomposition in U–50Zr alloy10.1016/j.mtla.2020.100592 ↗
24. Defect production and segregation induced by collision cascades in U-10Zr alloy10.1016/j.jnucmat.2019.151769 ↗
25. Simulated microstructural and compositional evolution of U-Pu-Zr alloys using the Potts-phase field modeling technique10.1007/s11661-018-4922-7 ↗
26. Thermochemically-informed mass transport model for interdiffusion of U and Zr in irradiated U-Pu-Zr fuel with fission products10.1016/j.jnucmat.2021.153089 ↗
27. Development and verification of a phase-field model for the equilibrium thermodynamics of U-Pu-Zr10.1016/j.anucene.2018.10.029 ↗
28. The microstructure and thermodynamic behavior of as-cast U-24Pu-15Zr: Unexpected results and recommendations for U-Pu-Zr fuel research methodology10.1016/j.jnucmat.2019.02.039 ↗
29. Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-910.1016/j.jnucmat.2017.07.040 ↗
30. The application of synchrotron micro-computed tomography to characterize the three-dimensional microstructure in irradiated nuclear fuel10.1016/j.jnucmat.2020.152161 ↗
31. α-U and ω-UZr 2 in neutron irradiated U-10Zr annular metallic fuel10.1016/j.jnucmat.2020.152536 ↗
32. Fuel-cladding chemical interaction of a prototype annular U-10Zr fuel with Fe-12Cr ferritic/martensitic HT-9 cladding10.1016/j.jnucmat.2020.152588 ↗
33. A study of constituent redistribution in U-Zr fuels using quantitative phase-field modeling and sensitivity analysis10.1016/j.jnucmat.2019.05.053 ↗
34. Characterization of metallic fuel for minor actinides transmutation in fast reactor10.1016/j.pnucene.2016.04.004 ↗
35. Investigation of constituent redistribution in U-Pu-Zr fuels and its dependence on varying Zr content10.1016/j.jnucmat.2021.153301 ↗
36. Electron probe microanalysis of irradiated FUTURIX-FTA U-Pu-Zr alloy with minor actinides10.1016/j.jnucmat.2019.151745 ↗
37. Investigation of fuel microstructure at the top of a metallic fuel pin after a reactor overpower transient10.1016/j.jnucmat.2020.152711 ↗
38. Capriotti · 2019
39. Behavior of metallic fast reactor fuels during an overpower transient10.1016/j.jnucmat.2021.153304 ↗
40. Studies on fuel-cladding chemical interaction between U−10 wt%Zr alloy and T91 steel10.1016/j.jnucmat.2018.10.041 ↗
41. U-10Zr and U-5Fs: Fuel/cladding chemical interaction behavior differences10.1016/j.jnucmat.2019.151840 ↗
42. Controlling FCCI with Pd in Metallic Fuel
43. Diffusion behaviors between metallic fuel alloys with Pd addition and Fe10.1016/j.jnucmat.2019.07.028 ↗
44. Nd, SbNd and Sb3Nd4 and their interactions with the cladding alloy HT910.1016/j.jnucmat.2020.152387 ↗
45. Characterization of U-Zr fuel with alloying additive Sb for immobilizing fission product lanthanides10.1016/j.jnucmat.2017.10.039 ↗
46. Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides10.1016/j.jnucmat.2018.08.017 ↗
47. Interactions and immobilization of lanthanides with dopants in uranium-based metallic fuels10.1016/j.jnucmat.2020.152372 ↗
48. Assessment of Te as a U-Zr fuel additive to mitigate fuel-cladding chemical interactions10.1016/j.jnucmat.2018.10.050 ↗
49. Reexamination of a U-Zr diffusion couple experiment using quantitative phase-field modeling and sensitivity analysis10.1016/j.jnucmat.2019.151929 ↗
50. An estimation of the thermal properties of Pu-rich metallic fuel10.1155/2019/7263721 ↗
51. Molar heat capacity of uranium-rich U-Zr-Nb and U-Zr-Mo alloys10.1016/j.jnucmat.2020.152427 ↗
52. Intragranular thermal transport in U-50Zr10.1016/j.jnucmat.2020.152145 ↗
53. Thermophysical and thermomechanical properties of U-23wt.%Pu-6wt.%Zr alloy fuel: Computational and high temperature mass spectrometric studies
54. Theoretical study on stability, mechanical, and thermodynamic properties of (Pu, Zr)N10.1016/j.jnucmat.2019.01.037 ↗
55. Shear strength of nanocrystalline delta phase Pu-Ga alloys: atomistic simulations10.1016/j.jnucmat.2019.07.002 ↗
56. Temperature and composition dependent thermal conductivity model for U-Zr alloys10.1016/j.jnucmat.2018.05.021 ↗
57. Hales · 2016
58. Calculation of the displacement energy of a and g uranium10.1016/j.jnucmat.2018.05.039 ↗
59. Evaluation of the anisotropic grain boundaries and surfaces of α-U via molecular dynamics10.1016/j.jnucmat.2021.153072 ↗
60. Atomistic calculations of the surface energy as a function of composition and temperature in gamma U-Zr to inform fuel performance modeling10.1016/j.jnucmat.2020.152271 ↗
61. Integrating Advanced Modeling and Accelerated Testing for a Modernized Fuel Qualification Paradigm10.1080/00295450.2020.1826272 ↗