In-situ ion irradiation of fission products in a spent UO2 fuel
Source abstract
Abstract
This study investigates the behavior of fission gas bubbles and five metal precipitates (5MPs) (Mo, Ru, Rh, Tc, Pd) in spent uranium dioxide (UO 2 ) fuel under various ion irradiation doses, temperatures, and flux conditions. Utilizing in-situ ion irradiation and advanced transmission electron microscopy, we analyzed the evolution of fission gas bubbles and 5MPs in UO 2 samples from the Belgium Reactor 3 (BR-3). Our findings reveal significant shrinkage of fission gas bubbles and 5MPs with increasing irradiation dose, accompanied by a decrease in pair density. We demonstrate that ion irradiation induces a homogeneous re-solution process where individual atoms are ejected from bubbles and precipitates, leading to their dissolution and subsequent re-precipitation in the matrix. This study provides critical insights into the dynamic behavior of fission products under irradiation, facilitating the development of predictive models and contributing to the optimization of nuclear fuel performance and safety.
Source: openalex_inverted_index · Quality: baseline
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 (48)
Show source-provided references
1. Fission gas release from UO2 nuclear fuel: a review10.1016/j.jnucmat.2018.08.019 ↗
2. 2.18 - radiation effects in UO2
3. Thermal energy transport in oxide nuclear fuel10.1021/acs.chemrev.1c00262 ↗
4. Phase-field modeling of gas bubbles and thermal conductivity evolution in nuclear fuels10.1016/j.jnucmat.2009.03.017 ↗
5. Olander · 1976
6. Multiscale development of a fission gas thermal conductivity model: Coupling atomic, meso and continuum level simulations10.1016/j.jnucmat.2013.05.008 ↗
7. Electron probe micro-analysis of irradiated UO210.1016/0022-3115(65)90166-2 ↗
8. Metallic fission-product inclusions in irradiated oxide fuels10.1016/0022-3115(68)90045-7 ↗
9. The fate of the epsilon phase (Mo-Ru-Pd-Tc-Rh) in the UO2 of the Oklo natural fission reactors10.1524/ract.2006.94.9-11.749 ↗
10. Corrosion testing of a simulated five-metal epsilon particle in spent nuclear fuel
11. Thermodynamic treatment of noble metal fission products in nuclear fuel10.1016/j.jnucmat.2006.11.014 ↗
12. The chemical state of the fission products in oxide fuels10.1016/0022-3115(85)90460-X ↗
13. The inhibiting effects of hydrogen on the corrosion of uranium dioxide under¨ nuclear waste disposal conditions10.1016/j.jnucmat.2005.04.070 ↗
14. U.S. Nuclear Regulatory Commission, Safety Evaluation Report Related to the License Renewal of the Donald C. Cook Nuclear Plant, Units 1 and 2, Docket Nos. 50-315 and 50-316, License Nos. DPR-58 and DPR-74, https://www.nrc.gov/docs/ML2413/ML24132A009.pdf (2024), Accession Number: ML24132A009.
15. The high burn-up structure in nuclear fuel10.1016/S1369-7021(10)70221-2 ↗
16. A critical review of high burnup fuel fragmentation, relocation, and dispersal under loss-of-coolant accident conditions10.1016/j.jnucmat.2020.152750 ↗
17. Effects of high burn-up on oxide ceramic fuels
18. Metallographic examinations and hydrogen measurements of highburnup spent nuclear fuel cladding10.1016/j.jnucmat.2023.154833 ↗
19. Characterization of the radial microstructural evolution in LWR UO2 using electron backscatter diffraction10.1016/j.jnucmat.2023.154605 ↗
20. Raman micro-` spectroscopy of UOX and MOX spent nuclear fuel characterization and oxidation resistance of the high burn-up structure10.1016/j.jnucmat.2014.12.072 ↗
21. High burnup structure formation in U-Mo fuels10.1016/j.jnucmat.2022.153617 ↗
22. Transmission electron microscopy observation on irradiation-induced microstructural evolution in high burn-up UO2 disk fuel10.1016/S0168-583X(02)00622-5 ↗
23. Restructuring in high burnup UO2 studied using modern electron microscopy10.1016/j.jnucmat.2018.05.077 ↗
24. The fission gas bubble distribution in uranium dioxide from high temperature irradiated SGHWR fuel pins10.1016/0022-3115(77)90117-9 ↗
25. Electron microscope observation of the fission-gas bubble distribution in UO2
26. In situ TEM study of temperatureinduced fission product precipitation in UO210.1016/j.nimb.2008.03.158 ↗
27. In situ TEM observation of dislocation evolution in Kr-irradiated UO2 single crystal10.1016/j.jnucmat.2013.06.050 ↗
28. Bubble formation and Kr distribution in Kr-irradiated UO210.1016/j.jnucmat.2014.09.026 ↗
29. Challenges to the use of ion irradiation for emulating reactor irradiation10.1557/jmr.2015.73 ↗
30. In situ TEM studies of microstructure evolution under ion irradiation for nuclear engineering applications10.1017/S143192761006321X ↗
31. Nanoscale chemical compositional analysis with an innovative S/TEM-EDX system
32. Noble gas constraints on spent fuel irradiation histories10.1007/s10967-023-08946-w ↗
33. Image processing with ImageJ
34. EELS log-ratio technique for specimen-thickness measurement in the TEM10.1002/jemt.1060080206 ↗
35. The stopping and range of ions in matter
36. High voltage electron microscope observations of UO210.1016/0022-3115(85)90077-7 ↗
37. Predicting damage production in monoatomic and multi-elemental targets using stopping and range of ions in matter code: challenges and recommendations10.1016/j.cossms.2019.06.001 ↗
38. Oxide fuel transients10.1016/0022-3115(89)90187-6 ↗
39. Microstructural examination of oxidized spent PWR fuel by transmission electron microscopy10.1016/0022-3115(89)90221-3 ↗
40. Williams · 2009
41. Multislice simulation of transmission electron microscopy imaging of helium bubbles in Fe10.1093/jmicro/dfs065 ↗
42. Molecular dynamics study of Xe bubble re-solution in UO210.1016/j.jnucmat.2011.10.010 ↗
43. The influence of irradiation on the nucleation of gas bubbles in reactor fuels10.1016/0022-3115(68)90047-0 ↗
44. The stability of precipitates in an irradiation environment10.1016/0022-3115(72)90043-8 ↗
45. Ion-beam-induced migration and its effect on concentration profiles10.1016/0029-554X(80)91264-1 ↗
46. Radiation enhanced diffusion in UO2 and (U, Pu)O210.1080/00337578308224715 ↗
47. Dislocation loop evolution in Kr-irradiated ThO210.1111/jace.18478 ↗
48. Was · 2007