Post-irradiation characterization of a high burnup mixed oxide fuel rod with minor actinides
Source abstract
Abstract
The Advanced Fuels Campaign performed a series of irradiation tests of minor actinide-bearing mixed oxide fuel (MA-MOX), the so-called AFC-2C&D experiments, to investigate the transmutation of long-lived transuranic actinide isotopes contained in spent nuclear fuel via fast reactor technology at burnups exceeding 10 % fission of initial metallic atoms. This manuscript reports the test results derived from one of the five MA-MOX rodlets taken to higher burnup in the AFC-2D irradiation. This includes both non-destructive investigations, such as gamma and neutron spectrometry, and destructive investigations, such as fission gas release, ceramography, and chemical burnup analysis. In addition, the microstructure of the fuel was investigated using advanced electron microscopy techniques including electron backscatter diffraction (EBSD) and transmission electron microscopy (TEM). It was observed with EBSD that the pellet had subdivision of the grains and the TEM observed migration of cladding material into the 5 metal precipitates in the fuel which could have been from the higher than desired oxygen/metal ratio. The TEM also showed an enrichment of Cr in fuel clad chemical interaction (FCCI) layer.
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 (69)
Show source-provided references
1. Maximum efficiency nuclear waste transmutation10.1016/j.anucene.2018.10.034 ↗
2. Assessment of the potential for criticality in the far field of a used nuclear fuel repository10.1016/j.anucene.2018.09.028 ↗
3. Rock-welding materials development for deep borehole nuclear waste disposal10.1016/j.matchemphys.2018.09.023 ↗
4. Transmutation of minor actinides in the pressure water reactors10.1016/j.anucene.2013.09.042 ↗
5. Minor actinide transmutation characteristics in AP100010.1016/j.anucene.2018.01.031 ↗
6. “Minor actinides transmutation on pressurized water reactor burnable poison rods10.1016/j.anucene.2017.06.039 ↗
7. A review of microstructural features in fast reactor mixed oxide fuels10.1016/j.jnucmat.2018.05.076 ↗
8. “Analysis of the impacts of homogeneous minor actinides loading in low void effect sodium fast reactor cores10.1016/j.anucene.2018.10.044 ↗
9. The results of the transmutation of fission fragments in the spectrum of neutrons of thermal and fast reactors10.1016/j.nucet.2017.07.004 ↗
10. “Transmutation characteristics of minor actinides in low aspect ratio tokamak fusion reactor10.1016/j.fusengdes.2014.05.029 ↗
11. Neutronics analysis of minor actinides transmutation in a fusion-driven subcritical system10.1016/j.fusengdes.2013.04.021 ↗
12. “Construction of minor actinides reduction scenario in Japan utilizing fusion reactors” Prog10.1016/j.pnucene.2017.11.003 ↗
13. Transmutation performance of uniform and nonuniform distributions of plutonium and minor actinides in TRIGA Mark II ADS reactor10.1016/j.anucene.2018.07.012 ↗
14. Optimization of composite metallic fuel of minor actinide transmutation in an accelerator-driven system10.1016/j.jnucmat.2010.11.093 ↗
15. Flexibility of ADS for minor actinides transmutation in different two-stage PWR-ADS fuel cycle scenarios10.1016/j.anucene.2017.08.037 ↗
16. Recent progress on minor-actinide-bearing oxide fuel fabrication at CEA Marcoule10.1016/j.jnucmat.2013.02.079 ↗
17. A small lead-cooled reactor with improved AM-burning and non-proliferation characteristics10.1016/j.anucene.2018.08.043 ↗
18. ASTRID-like Fast Reactor Cores for Burning Plutonium and Minor Actinides10.1016/j.egypro.2014.11.863 ↗
19. Plutonium and Minor Actinides incineration option using innovative Na-cooled fast reactors: Impacting on phasing-out and on-going fuel cycles” Prog10.1016/j.pnucene.2014.07.034 ↗
20. Testing fast reactor fuels in a thermal reactor10.1016/j.nucengdes.2017.12.034 ↗
21. Irradiation of AFC-2C and -2D Oxide Fuels for Actinide Transmutation in the ATR
22. Accelerator Driven Subcritical Systems”10.1016/B978-0-12-819725-7.00093-3 ↗
23. Baseline Postirradiation Examination of Fuel Rodlets from the AFC-2D Experiment
24. Radial redistribution of actinides in irradiated FR-MOX fuels10.1016/j.jnucmat.2009.01.010 ↗
25. Short-term irradiation behavior of low-density americium-doped uranium-plutonium mixed oxide fuels irradiated in a fast reactor10.1016/j.jnucmat.2010.11.027 ↗
26. Electron microscopy characterization of fast reactor MOX Joint Oxyde-Gaine (JOG)10.1016/j.jnucmat.2019.151964 ↗
27. Post-irradiation examinations of annular mixed oxide fuels with average burnup 4 and 5 % FIMA10.1016/j.jnucmat.2020.152076 ↗
28. Comparison of the radial effects of burnup on fast reactor MOX fuel microstructure and solid fission products10.1016/j.jnucmat.2020.152003 ↗
29. EBSD and TEM characterization of high burn-up mixed oxide fuel10.1016/j.jnucmat.2013.10.037 ↗
30. 2.03- Fuel Performance of Fast Spectrum Oxide Fuel” Compr
31. Fuels for sodium-cooled fast reactors: US perspective10.1016/j.jnucmat.2007.05.010 ↗
32. A Review of Fast Reactor Program in Japan
33. Microstructural characterization of high burn-up mixed oxide fast reactor fuel10.1016/j.jnucmat.2013.05.067 ↗
34. High Burnup irradaition performance of annular fuel pins irradaited in fast reactor PFR
35. Transmutation of neptunium and americium in a fast neutron flux: EPMA results and KORIGEN predictions for the superfact fuels10.1016/0022-3115(94)00649-0 ↗
36. Some Specific Aspects of Homogeneous Americium-and Neptunium-Based Fuels Transmutation Through the Outcomes of the Superfact Experiment in Phénix Fast Reactor10.13182/NT97-A35382 ↗
37. Microstructure and elemental distribution of americium-containing uranium plutonium mixed oxide fuel under a short-term irradiation test in a fast reactor10.1016/j.jnucmat.2008.12.028 ↗
38. Restructuring and redistribution of actinides in Am-MOX fuel during the first 24 h of irradiation10.1016/j.jnucmat.2013.01.351 ↗
39. Restructuring and redistribution of actinides in Am-MOX fuel during the first of irradiation10.1016/j.jnucmat.2013.01.351 ↗
40. Application of the UMACS process to highly dense U1-xAmxO2±δ MABB fuel fabrication for the DIAMINO irradiation10.1016/j.jnucmat.2012.07.018 ↗
41. Description and thermal simulation of the DIAMINO irradiation experiment of transmutation fuel in the OSIRIS reactor” Prog10.1016/j.pnucene.2019.01.012 ↗
42. The results of the irradiation experiment MARIOS on americium transmutation” Ann10.1016/j.anucene.2013.05.043 ↗
43. SPHERE: Irradiation of sphere-pac fuel of UPuO2-x containing 3% Americium” 275 Nucl
44. Current start of partitioning and transmutation studies for advanced nuclear fuel cycles10.1016/j.anucene.2021.108239 ↗
45. “AFC2-C/D Fuel Pellet Data Package
46. Testing Fast Reactor Fuels in a Thermal Reactor: A Comparison Report
47. Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel10.1016/j.jnucmat.2013.09.035 ↗
48. Neutron Radiography of Irradiated Nuclear Fuel at Idaho National Laboratory10.1016/j.phpro.2015.07.068 ↗
49. Burnup Determination for Fast Reactor Fuels: A Review and Status of the Nuclear Data and Analytical Chemistry Methodology Requirements
50. An analysis of nuclear fuel burnup in the AGR-1 TRISO fuel experiment using gamma spectrometry, mass spectrometry, and computational simulation techniques10.1016/j.nucengdes.2014.07.041 ↗
51. On the rim effect in high burnup UO2 LWR fuels10.1016/0022-3115(92)90428-N ↗
52. Restructuring in high burnup UO2 studied using modern electron microscopy” J10.1016/j.jnucmat.2018.05.077 ↗
53. Modeling of central void formation in LWR fuel pellets due to high-temperature restructuring10.1016/j.net.2018.07.003 ↗
54. Modeling porosity migration in LWR and fast reactor MOX fuel using the finite element method10.1016/j.jnucmat.2018.05.041 ↗
55. The high burn-up structure in nuclear fuel10.1016/S1369-7021(10)70221-2 ↗
56. Microstructural characterization of high burn-up mixed oxide fast reactor fuel10.1016/j.jnucmat.2013.05.067 ↗
57. Microhardness and Young's modulus of high burn-up UO2 fuel” J10.1016/j.jnucmat.2016.07.015 ↗
58. Detailed characterizations of high burn-up structures in oxide fuels10.1016/j.jnucmat.2007.04.037 ↗
59. Focused ion beam-scanning electron microscope examination of high burn-up UO2 in the center of a pellet” Nucl
60. Distributions of volatile fission products in or near the fuel-cladding of the FBR MOX fuel pins irradiated to high burn-up10.1016/j.jnucmat.2005.04.054 ↗
61. Change of fuel-to-cladding gap width with the burn-up in FBR MOX fuel irradiated to high burn-up10.1016/j.jnucmat.2004.01.003 ↗
62. Characterization of solid fission products in 13.7% FIMA MOX fuel using electron microscopy techniques10.1016/j.jnucmat.2019.06.042 ↗
63. TEM characterization of high burnup fast reactor MOX fuel10.1016/j.jnucmat.2019.151794 ↗
64. Corrosion behavior of 9CrODS steel by simulated fission product cesium and tellurium10.1016/j.jnucmat.2013.04.017 ↗
65. Reaction a l’interface gaine (acier inoxydable) combustible (oxyde mixte (UPu)O2±x) dans les elements combustibles irradies10.1016/0022-3115(72)90063-3 ↗
66. Cladding interactions in mixed oxide irradiated fuels10.1016/0022-3115(70)90013-9 ↗
67. Role de l’iodure de cesium sur le developpement des reactions combustible-gaine10.1016/0022-3115(76)90141-0 ↗
68. On the CsTe Fission Product-Induced attach and embrittlement of stainless steel cladding in oxide fuel pins10.1016/0022-3115(85)90410-6 ↗
69. The corrosion product of Cs-Te corrosive compound with 11Cr-Ferritic Martensitic Steel and 9Cr-Oxide Dispersion strengthened steel10.1016/j.jnucmat.2015.02.011 ↗