journal article·2023-08Open access

Diffusion of Xe and Kr implanted at low concentrations in UO2 as a function of temperature – An experimental study

M. Gérardin, E. Gilabert, D. Horlait, M-F. Barthe, G. Carlot

Abstract

Fission gases production and release have a large impact on uranium dioxide fuel performance. To predict fuel properties in pile, a better understanding of the fission gas behaviour in uranium dioxide is needed. UO$_2$ samples were implanted with Xe or Kr at low doses to avoid trapping by irradiation defects and/or gas clusters. The release rates of Xe and Kr were studied at temperatures ranging up to 1400°C. Results show an excellent agreement with the substantial literature on xenon diffusion in irradiated UO$_2$.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Radioactive element chemistry and processing · Nuclear reactor physics and engineering

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (73)

Show source-provided references
1. Bailly · 1996
2. Unit mechanisms of fission gas release: current understanding and future needs10.1016/j.jnucmat.2018.03.016 ↗
3. Fission gas release from UO2 nuclear fuel: a review
4. Gas release mechanisms in UO2 - A critical review10.1080/00337578008207118 ↗
5. U and Xe transport in UO2 ± x : density functional theory calculations10.1103/PhysRevB.84.054105 ↗
6. Mechanism for transient migration of xenon in UO2
7. Ab initio energetics of some fission products (Kr, I, Cs, Sr and He) in uranium dioxide10.1016/S0022-3115(02)00907-8 ↗
8. Ab initio modeling of the behavior of helium and xenon in actinide dioxide nuclear fuels10.1016/j.jnucmat.2006.02.048 ↗
9. Molecular modeling of transmutation fuels and targets10.1016/S0022-3115(03)00179-X ↗
10. Location of krypton atoms in urnaium dioxide10.1016/S0022-3115(99)00127-0 ↗
11. First-principles study of noble gas impurities and defects in UO210.1103/PhysRevB.84.134111 ↗
12. Atomic diffusion mechanism of Xe in UO210.1016/j.jnucmat.2008.04.013 ↗
13. First-principales theory for helium and xenon diffusion in uranium dioxide10.1016/j.jnucmat.2008.12.024 ↗
14. Thermodynamics of fission products in UO2±x10.1088/0953-8984/21/43/435602 ↗
15. Determination of krypton diffusion coefficients in uranium dioxide using atomic scale calculations10.1021/acs.inorgchem.6b01560 ↗
16. Atomistic modeling of intrinsic and radiation-enhanced fission gas (Xe) diffusion in UO2±x : implications for nuclear fuel performance modeling10.1016/j.jnucmat.2014.03.041 ↗
17. The stability of fission products in uranium dioxide
18. On the solution and migration of single Xe atoms in uranium dioxide – An interatomic potentials study10.1016/j.jnucmat.2010.08.013 ↗
19. Free energy of Xe incorporation at point defects and in nanovoids and bubbles in UO210.1103/PhysRevB.85.144102 ↗
20. A computational study of the effect of Xe concentration on the behavior of single Xe atoms in UO210.1016/0022-3115(95)00131-X ↗
21. Simulation of radiation driven fission gas diffusion in UO2, ThO 2 and PuO210.1016/j.jnucmat.2016.09.013 ↗
22. Atomistic modeling of out-of-pile xenon diffusion by vacancy clusters in UO210.1016/j.jnucmat.2019.03.050 ↗
23. Effect of stoichiometry on diffusion of xenon in UO210.1016/0022-3115(72)90080-3 ↗
24. Diffusion of xenon 1300 in UO2 single crystals
25. Microstructural change and its influence on fission gas release in high burnup UO2 fuel10.1016/0022-3115(92)90455-T ↗
26. A new thermo-desorption laser-heating setup for studying noble gas diffusion and release from materials at high temperatures10.1063/5.0068858 ↗
27. Xenon diffusion in UO2 - some complicating factors10.1016/0022-3115(64)90123-0 ↗
28. Effect of irradiation and dopant concentration on the migration of xenon in UO2
29. Temperature dependence of diffusivity of xenon in high dose irradiated UO210.1016/0022-3115(89)90581-3 ↗
30. Experimental study of the diffusion of Xe and Kr implanted at low concentrations in UO2 and determination of their trapping mechanisms10.1016/j.jnucmat.2021.153174 ↗
31. Long G., Davies D., and J.R. Findlay, “Diffusion of fission products in uranium dioxide and uranium monocarbide,” UKAEA Memo AERE-M1251, 1964.
32. Diffusion von Xe-133 in Uranoxyd verschiedenen Sauerstoffgehaltes10.1515/zna-1959-5-617 ↗
33. D. Davies and G. Long, “The emission of xenon-133 from lightly irradiated uranium dioxide spheroids and powders.,” vol. AERE-R 4347, 1963.
34. A.B. Auskern, “The diffusion of krypton 85 from uranium dioxide powder,” US Rep. WAPD-TM-185, 1960.10.2172/4193604 ↗
35. A.H. Booth and G.T. Rymer, “Determination of the diffusion constant of fission xenon on UO2 crystals and sintered compacts,” AECL-CRDC-720.
36. Effect or trapping in the release of recoil injected gases from solids10.1016/0029-554X(70)90043-1 ↗
37. A calculation on the migration of fission gas in material exhibiting precipitation and re-solution of gas atoms under irradiation10.13182/NSE69-A20676 ↗
38. Theory of diffusion-limited precipitation10.1016/0022-3697(58)90053-2 ↗
39. The role of bubbles in fission gas release from uranium dioxide10.1016/0022-3115(69)90178-0 ↗
40. A new fission-gas release model10.1016/0022-3115(83)90176-9 ↗
41. An analysis of the thermodynamics of gas atoms in very small bubbles10.1016/0022-3115(83)90066-1 ↗
42. A mechanism for fission gas release from high temperature fuel10.1016/0022-3115(85)90437-4 ↗
43. Xenon-133 diffusion and trapping in single crystal uranium dioxide10.1002/pssa.2210140236 ↗
44. “Active oxide polishing suspensions - brochure.” Struers, 2006.
45. D. Zipperian, “Colloidal silica polishing.” PACE Technologies - Quality Matters Newsletter, 2003.
46. S. Massara and C. Guéneau, “Thermodynamics of advanced fuels – international database,” vol. NEA News, no. 32, p. 24, 2014.
47. J.F. Ziegler, J.P. Biersack, and U. Littmark, “The stopping and range of ions in matter,” 2008.
48. Study on deceleration of ions in diatomic target
49. High voltage electron microscope observations of UO210.1016/0022-3115(85)90077-7 ↗
50. Helium interaction with vacancy-type defects created in silicon carbide single crystal10.1016/j.jnucmat.2013.01.288 ↗
51. Study of radiogenic helium diffusion in the β-thorium phosphate diphosphate ceramic10.1016/j.jnucmat.2007.05.038 ↗
52. Thermodynamic assessment of the uranium–oxygen system10.1016/S0022-3115(02)00878-4 ↗
53. Release of xenon from sintered UO2 at low temperatures
54. Release of xenon from low-dose irradiated thoria pellets10.1016/0022-3115(77)90094-0 ↗
55. An investigation into the influence of implanted oxygen on krypton behaviour in uranium dioxide during annealing10.1016/0022-3115(94)90329-8 ↗
56. The diffusion behavior of fission xenon in uranium dioxide
57. Thermal evolution spectrometry of low energy inert gas ions injected into polycrystalline UO210.1016/0042-207X(74)90087-6 ↗
58. First study of uranium self-diffusion in UO2 by SIMS10.1016/S0022-3115(98)00482-6 ↗
59. A study of point defects in UO2+x and their impact upon fuel properties, Thesis
60. New estimates for the sublimation rate for ice on the moon10.1016/j.icarus.2006.08.024 ↗
61. High-temperature thermodynamic properties of uranium dioxide10.1063/1.1743156 ↗
62. Experimental diffusion of Kr in UO2+x as a function of stoichiometry: tiny stoichiometry deviations, great effects
63. P. Terlouw and M.G.R. Vogelaar, “Kapteyn Package: tools for developing astronomical applications, Astrophysics Source Code Library.” 2016.
64. The diffusion coefficients of gaseous and volatile species during the irradiation of uranium dioxide10.1016/0022-3115(82)90419-6 ↗
65. Xenon diffusion in single crystal and sintered UO2
66. P.V. Uffelen, “Use of advanced simulations in fuel performance codes,” NEA/NSC/R, vol. 5, p. 7, 2015.
67. A review of nuclear fuel performance codes10.1016/j.pnucene.2005.01.004 ↗
68. A review of fuel performance modelling10.1016/j.jnucmat.2018.12.037 ↗
69. A new mechanistic code SFPR for modeling of single fuel rod performance under various regimes of LWR operation10.1016/j.nucengdes.2011.05.032 ↗
70. J. Rest, S.A. Zawadzki, FASTGRASS: a mechanistic model for the prediction of Xe, I, Cs, Te, Ba, and Sr release from nuclear fuel under normal and severe-accident conditions, NUREG/CR-5840, ANL–92/3 (1992).10.2172/7255051 ↗
71. SCIANTIX: a new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes10.1016/j.jnucmat.2020.152042 ↗
72. Largenton, Approach to better assess fission gas behaviors, applicable to fuels with complex microstructures
73. MARGARET: a comprehensive code for the description of fission gas behavior10.1016/j.nucengdes.2011.03.044 ↗