journal article·2020-04Open access

Three-dimensional bubble reconstruction in high burnup UO2

Casey McKinney, Rachel Seibert, Grant Helmreich, Assel Aitkaliyeva, Kurt Terrani

Abstract

Abstract In light water reactor (LWR) UO2 fuels, the evolution of volatile fission products is one of the critical areas of fuel behavior that is yet to be fully understood. In UO2 irradiated to high burnups, it is well known that most released fission gases come from the central region of the fuel as opposed to the highly porous high burnup structure (HBS) on the periphery of the pellets. However, fuels with and without interconnected bubble networks at the fuel center showed high to moderate release fractions, which conceals the mechanisms responsible for the gas release in the latter scenario. In this work, focused ion beam tomography was used to investigate the three-dimensional bubble structure in an irradiated LWR UO2 fuel pellet with high degree of fission gas retention so that the degree of bubble interconnection could be assessed. Six radial locations with different burnups and temperatures were serially sectioned and imaged to reconstruct the three-dimensional bubble structure. As expected, the highest porosity was observed at the periphery of the fuel (HBS). The porosity then decreased towards the pellet center, except for the centermost location. This location had a slightly higher porosity than its adjacent mid-radial location, which was attributed to the temperature difference between the two locations. This study provides a first-time volumetric evaluation of the porosity at different radial locations on a UO2 fuel pellet. During this investigation, no significant bubble interconnection was noted at any of the six radial locations.
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 (29)

Show source-provided references
1. Olander · 1976
2. Fission gas release from UO2 nuclear fuel: a review10.1016/j.jnucmat.2018.08.019 ↗
3. Booth · 1957
4. A calculation on the migration of fission gas in material exhibiting precipitation and re-solution of gas atoms under irradiation10.13182/NSE69-A20676 ↗
5. Re-solution of fission gas-A review: Part I. Intragranular bubbles10.1016/j.jnucmat.2006.03.010 ↗
6. The distribution of intragranular fission gas bubbles in UO2 during irradiation10.1016/0022-3115(71)90044-4 ↗
7. The development of grain-face porosity in irradiated oxide fuel10.1016/j.jnucmat.2003.10.008 ↗
8. Fission product release and microstructure changes during laboratory annealing of a very high burn-up fuel specimen10.1016/j.jnucmat.2008.03.006 ↗
9. Molecular dynamics study of Xe bubble re-solution in UO210.1016/j.jnucmat.2011.10.010 ↗
10. The high burn-up structure in nuclear fuel10.1016/S1369-7021(10)70221-2 ↗
11. Temperature and fission rate effects on the rim structure formation in a UO2 fuel with a burnup of 7.9% FIMA10.1016/S0022-3115(97)00280-8 ↗
12. SIMS analysis of an UO 2 fuel irradiated at low temperature to 65MWd/kgHM10.1016/j.jnucmat.2009.06.017 ↗
13. Comments on the threshold porosity for fission gas release in high burn-up fuels10.1016/j.jnucmat.2004.03.009 ↗
14. The morphology and growth rate of interlinked porosity in irradiated UO210.1016/0022-3115(73)90185-2 ↗
15. Focused ion beam-scanning electron microscope examination of high burn-up UO2 in the center of a pellet10.1016/j.net.2017.12.002 ↗
16. On the condition of UO2 nuclear fuel irradiated in a PWR to a burn-up in excess of 110 MWd/kgHM10.1016/j.jnucmat.2016.08.023 ↗
17. Critical assessment of the pore size distribution in the rim region of high burnup UO2 fuels10.1016/j.jnucmat.2016.08.010 ↗
18. Ruzauskas · 2001
19. Restructuring in high burnup UO2 studied using modern electron microscopy10.1016/j.jnucmat.2018.05.077 ↗
20. Fission gas release from UO2 pellet at high burnup
21. Tverberg · 2016
22. Summary of observed fission gas release behaviour in selected experiments performed at the Halden Reactor Project
23. LAMDA: irradiated-materials microscopy at Oak Ridge national laboratory10.1017/S1431927615005814 ↗
24. Young’s modulus evaluation of high burnup structure in UO2 with nanometer resolution10.1016/j.jnucmat.2018.04.004 ↗
25. EPMA and SEM of fuel samples from PWR rods with an average burn-up of around 100 MWd/kgHM10.1016/S0022-3115(01)00753-X ↗
26. The diffusion coefficients of gaseous and volatile species during the irradiation of uranium dioxide10.1016/0022-3115(82)90419-6 ↗
27. Stereological evolution of the rim structure in PWR-fuels at prolonged irradiation: dependencies with burn-up and temperature10.1016/j.jnucmat.2006.02.095 ↗
28. A theory of swelling and gas release for reactor materials10.1016/0022-3115(64)90002-9 ↗
29. Three-dimensional simulation of threshold porosity for fission gas release in the rim region of LWR UO2 fuel10.1016/S0022-3115(03)00249-6 ↗