journal article·2009-12

Modelling of the spent fuel oxidation: Toward the operational model

J. Rouyer, A. Poulesquen, L. Desgranges, C. Ferry

Journal of Nuclear Materials· Volume 395· Issue 1-3
Publisher page

Abstract

Abstract As part of a long-lasting dry storage, the oxidation of the spent fuel linked to an accidental supply of oxygen into the spent fuel rod, may have consequences that must be assessed. Indeed, the oxidation of the UO2 fuel up to U3O8 phase brings about a volume swelling of about 31% together with a bulking which may increase the initial defect of the cladding and thus lead to the release of fission products which remains embedded in nanometric gains or fine particles. From the oxidation model first developed (grain model), a new model has been proposed to describe the oxidation of spent fuel. The latter is based on a transposition of the graded grain model for unirradiated powders to irradiated grains. The modification of the grain model concerns the structural evolutions and the stoichiometric ranges during the oxidation. The convolution between the irradiated grain model and the propagation of the oxidation front along the grain boundaries allow to describe the oxidation kinetics of a spent fuel fragment. A criterion of grain breaking, based on experimental observations, has been proposed. The model has been parametrized from the experimental data of the literature and obtained as part of the French PRECCI’s program. The harmony between the model and the experimental data either in terms of mass gain curves or of the oxygen diffusion coefficients in the UO2 matrix is satisfactory. From this mechanistic model, an operational model for dry storage is proposed. On one hand, a simplified model (qualitative one) allowing to link the operational parameters (irradiation history) such as the burn up, the linear power or else the released gas fraction to a time for cracks to appear in the grains has been proposed. This model allows to display the time for the fractures in the fuel to appear (or a time before fracturing) according to the review of the treated fuels. On the other hand, a predictive operational model taking only the temperature into account is proposed.
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 (24)

Show source-provided references
1. L. Desgranges, F. Charollais, I. Felines, C. Ferry, J. Radwan, A New Criterion for the Degradation of a Defective Spent Fuel Rod Under Dry Storage Conditions Based on Nuclear Ceramic Cracking, Scientific Basis for Nuclear Waste Management XXXII Meeting, MRS Proceeding, vol. 1124, 2008.10.1557/PROC-1124-Q02-06 ↗
2. B. Hanson, The Burn Up Dependence of Light Water Reactor Spent Fuel Oxidation, PNNL-11929 Report, 1998.10.2172/291169 ↗
3. McEachern · J. Nucl. Mater. · 1998 · 254 · 8710.1016/S0022-3115(97)00343-7 ↗
4. Rousseau · J. Nucl. Mater. · 2006 · 355 · 1010.1016/j.jnucmat.2006.03.015 ↗
5. A. Poulesquen, Modèle d’oxydation de grains: comparaisons aux données de la littérature, NT DPC/SECR 06-006 indice A, Personal Communication, 2006.
6. Taylor · J. Nucl. Mater. · 2005 · 344 · 20610.1016/j.jnucmat.2005.04.043 ↗
7. L. Desgranges, M.P. Ferroud-Plattet, H. Giacalone, I. Aubrun, J.M. Untrau, Bilan des expériences d’oxydation ménagées à 200°C menées au LECA et au LAMA dans le cadre du programme PRECCI, NT DEC/SA3C/L2EC – 006 – indice 0, Personal Communication, 2007.
8. Thomas · J. Nucl. Mater. · 1989 · 166 · 24310.1016/0022-3115(89)90221-3 ↗
9. Zacharie · J. Nucl. Mater. · 1998 · 255 · 8510.1016/S0022-3115(98)00039-7 ↗
10. Wasywich · Nucl. Technol. · 1992 · 104 · 30910.13182/NT93-A34893 ↗
11. Einziger · J. Nucl. Mater. · 1992 · 190 · 5310.1016/0022-3115(92)90075-V ↗
12. B. Hanson, Clad Degradation – Dry Unzipping, ANL-EBS-MD-000013 REV 00, 2000.
13. Thomas · J. Nucl. Mater. · 1993 · 201 · 31010.1016/0022-3115(93)90187-4 ↗
14. Poulesquen · J. Nucl. Mater. · 2007 · 362 · 40210.1016/j.jnucmat.2007.01.084 ↗
15. A. Poulesquen, L. Desgranges, C. Ferry, Modeling of Spent Fuel Oxidation at Low Temperature, Scientific Basis for Nuclear Waste Management XXX Meeting, MRS Proceeding, vol. 985, 2006.10.1557/PROC-985-0985-NN05-04 ↗
16. morphological and structural study
17. A.H. Booth, A Method of Calculating Fission Gas Diffusion from UO2 and Its Application to the X-2-F Loop Test, 1957 (AECL CRDC-721).
18. Uchida · J. Nucl. Sci. Technol. · 1993 · 30 · 75210.3327/jnst.30.752 ↗
19. Bevan · J. Solid State Chem. · 1986 · 61 · 110.1016/0022-4596(86)90002-2 ↗
20. Garrido · J. Nucl. Mater. · 2003 · 322 · 8710.1016/S0022-3115(03)00318-0 ↗
21. Menegon · J. Nucl. Mater. · 2008 · 378 · 110.1016/j.jnucmat.2008.04.008 ↗
22. Woodley · Nucl. Technol. · 1989 · 85 · 7410.13182/NT89-A34229 ↗
23. Desgranges · Inorg. Chem. · 2009
24. Kang · Thermochim. Acta · 2007 · 455 · 12910.1016/j.tca.2006.11.021 ↗