Thermal behaviour of caesium implanted in UO2: A comparative study with the xenon behaviour
Source abstract
Abstract
• SIMS and TEM techniques were combined to compare the thermal behaviour of Cs and Xe in UO 2 . • Both elements form bubbles with different growth kinetics. • At 1600 °C, caesium is found to be highly mobile in the UO 2 matrix while Xe distribution does not evolve.
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Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Radioactive element chemistry and processing
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References (57)
Show source-provided references
1. The IRSN's earliest assessments of the Fukushima accident's consequences for the terrestrial environment in Japan10.1051/radiopro/2012052 ↗
2. Clefs CEA no 53, Déchets radioactifs, des solutions en progrès continu (2005) ISSN 0298-6248.
3. Predicting material release during a nuclear reactor accident10.1038/nmat4224 ↗
4. Behaviour of fission products under severe PWR accident conditions the VERCORS experimental programme-Part 2: release and transport of fission gases and volatile fission products10.1016/j.nucengdes.2009.06.024 ↗
5. Releases of cesium and poorly volatile elements from UO2 and MOX fuels under severe accident conditions10.1080/18811248.2007.9711389 ↗
6. PHEBUS FP: a severe accident research programme for current and advanced light water reactors10.1016/S0029-5493(98)00257-X ↗
7. Cs and I-release source terms from irradiated LWR fuel10.1016/0022-3115(83)90205-2 ↗
8. Effect of redox conditions on the fission products release from irradiated oxide fuel10.1016/j.proche.2012.10.019 ↗
9. Fission product release and microstructure changes during laboratory annealing of a very high burn-up specimen10.1016/j.jnucmat.2008.03.006 ↗
10. Volatile fission product behavior during thermal annealing of irradiated UO2 fuel oxidized up to U3O810.1016/j.jnucmat.2007.03.174 ↗
11. Release of fission-products (Xe, I, Te, Cs, Mo and Tc) from polycrystalline UO210.1016/0022-3115(88)90115-8 ↗
12. Further observations on OCOM MOX fuel: microstructure in the vicinity of the pellet rim and fuel-cladding interaction10.1016/0022-3115(95)00191-3 ↗
13. Modelling nuclear fuel behaviour with TAF-ID: Calculations on the VERDON-1 experiment, representative of a nuclear severe accident10.1016/j.jnucmat.2019.05.027 ↗
14. Evidence of tellurium iodide compounds in a power-ramped irradiated UO2 fuel rod10.1016/j.jnucmat.2013.02.059 ↗
15. Experimental evidence of the formation of a new chemical phase in a power ramped UO2 nuclear fuel10.1016/j.jnucmat.2014.11.070 ↗
16. A.H. Booth, A method of calculating fission gas diffusion from UO2 fuel and its application to the X-2-f loop test, report CRDC no 721 (1957).
17. Migration behaviour of iodine in nuclear fuel10.1016/S0022-3115(01)00447-0 ↗
18. Thermal diffusion of iodine in UO2 and UO2+x10.1016/j.jnucmat.2007.03.272 ↗
19. Thermal diffusion of chlorine in uranium dioxide10.1524/ract.2006.94.9-11.705 ↗
20. Effect of the oxygen potential on the Mo migration and speciation in UO2 and UO2+x10.1021/acs.inorgchem.8b03076 ↗
21. SIMS analysis of 83Kr implanted UO210.1016/j.apsusc.2008.05.263 ↗
22. Kr implantation into heavy ion irradiated monolithic UeMo/Al systems: SIMS and SEM investigations10.1016/j.jnucmat.2015.12.039 ↗
23. Xenon migration in UO2: a SIMS study10.1016/j.pnucene.2011.10.009 ↗
24. Variable energy positron beam study of Xe-implanted uranium oxide10.1016/j.jnucmat.2012.07.035 ↗
25. Ziegler · 1985
26. High-voltage electron-microscope observations of UO210.1016/0022-3115(85)90077-7 ↗
27. Measurement of xenon in uranium dioxide (UO2) with SIMS10.1016/j.nimb.2003.08.033 ↗
28. SIMS Quantification in Si, GaAs, and diamond- an update10.1016/0168-1176(94)04136-U ↗
29. Marchand · 2012
30. Dynamic SIMS for materials analysis in nuclear science10.1116/1.5017027 ↗
31. Recent results of microstructural characterization of irradiated light water reactor Fuels using scanning and transmission electron microscopy10.1007/s11837-012-0483-1 ↗
32. Microstructure evolution in Xe-irradiated UO2 at room temperature10.1016/j.nimb.2014.03.018 ↗
33. Characterization of helium bubble size and faceting by electron holography10.1063/1.2216791 ↗
34. In situ TEM study of temperature-induced fission product precipitation in UO210.1016/j.nimb.2008.03.158 ↗
35. Influence of exogenous xenon atoms on the evolution kinetics of extended defects in polycrystalline UO2 using in situ TEM10.1016/j.jnucmat.2018.10.025 ↗
36. Radiation damage in uranium dioxide10.1080/14786436508228669 ↗
37. Irradiation-induced heterogeneous nucleation in uranium dioxide10.1016/j.physleta.2010.05.033 ↗
38. Molecular dynamics study of the bulk temperature effect on primary radiation damage in uranium dioxide10.1016/j.nimb.2014.12.008 ↗
39. Effect of temperature on bubble precipitation in uranium dioxide implanted with krypton and xenon ions10.1016/0022-3115(92)90475-Z ↗
40. An in situ TEM study of the evolution of Xe bubble populations in UO210.1016/j.nimb.2011.01.069 ↗
41. XAS characterisation of xenon bubbles in uranium dioxide10.1016/j.nimb.2008.03.180 ↗
42. Behavior of fission gases in nuclear fuel: XAS characterization of Kr in UO210.1016/j.jnucmat.2015.08.019 ↗
43. Atomic diffusion mechanism of Xe in UO210.1016/j.jnucmat.2008.04.013 ↗
44. U and Xe transport in UO2 +/- x: density functional theory calculations10.1103/PhysRevB.84.054105 ↗
45. Free energy of Xe incorporation at point defects and in nanovoids and bubbles in UO210.1103/PhysRevB.85.144102 ↗
46. Molecular dynamics simulation of Xe bubble nucleation in nanocrystalline UO2 nuclear fuel10.1016/j.jnucmat.2011.08.052 ↗
47. Ab initio study of solution energy and diffusion of caesium in uranium dioxide10.1016/j.jnucmat.2008.12.009 ↗
48. Fission-gas bubble behavior in uranium dioxide10.1016/0022-3115(93)90162-R ↗
49. Bubble diffusion to grain boundaries in UO2 and metals during annealing – a new approach10.1016/0022-3115(94)90218-6 ↗
50. An advanced model for intragranular bubble diffusivity in irradiated UO2 fuel10.1016/j.jnucmat.2008.01.026 ↗
51. Modelling intragranular bubble movement and fission gas release during post-irradiation annealing of UO2 using a meso scale and spatialized approach10.1016/j.jnucmat.2019.151874 ↗
52. The stability of fission products in uranium dioxide10.1098/rsta.1991.0062 ↗
53. Observations on the release of cesium from UO2 fuel10.1016/S0022-3115(96)00477-1 ↗
54. TEM study of alpha-damaged plutonium and americium dioxides10.1557/jmr.2015.37 ↗
55. Investigation of cation self-diffusion mechanisms in UO2 +/- x using molecular dynamics10.1016/j.jnucmat.2013.08.030 ↗
56. Fission gas release from UO2 nuclear fuel: a review10.1016/j.jnucmat.2018.08.019 ↗
57. Bubble evolution in Kr-irradiated UO2 during annealing10.1016/j.jnucmat.2017.09.036 ↗