Fission products chemistry in simulated PWR fuel up to 2100°C: Experimental characterisation and TAF-ID modelling
Source abstract
Abstract
The capabilities of the Thermodynamic of Advanced Fuels – International Database (TAF-ID) for reproducing the chemical behaviour of irradiated nuclear fuel in severe accident conditions were studied, by comparing calculation results to experimental observations. SIMFUELs samples containing UO2 + 11 elements (Ba, Ce, La, Mo, Nd, Pd, Rh, Ru, Sr, Y and Zr, in concentration representative of a 76 GWd•tU-1 Burn-up) were submitted to 1327°C in oxidizing conditions, and to 1800, 2000, and 2100°C under reducing ones. Samples were characterized by Electron Probe Micro-Analysis (EPMA), High-Resolution XRD, and X-ray Absorption Spectroscopy (XAS). Thermodynamic calculations reproduced accurately the solubility of fission products in the UO2 matrix, and the type and composition of minor oxide and most metallic phases. Calculations also explain metallic phases microstructure as a result of the progressive solidification of liquids. However, some features such as the U-Pd-Rh association could not be reproduced, due to the lack of a thermodynamic model for this ternary system.
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 (55)
Show source-provided references
1. The chemical state of LWR high-power rods under irradiation10.1016/0022-3115(79)90154-5 ↗
2. The chemical state of fission products in oxide fuels10.1016/0022-3115(85)90460-X ↗
3. 2.20 - fission product chemistry in oxide fuels
4. 2.07 - fission product chemistry in oxide fuels
5. Chemical interactions in water-cooled nuclear fuel: a thermochemical approach10.1016/0022-3115(88)90341-8 ↗
6. 14 - Advances in fuel chemistry during a severe accident: update after Fukushima Daiichi nuclear power station (FDNPS) accident
7. 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 ↗
8. Behaviour of fission products under severe PWR accident conditions. The VERCORS experimental programme – part 3: release of low-volatile fission products and actinides10.1016/j.nucengdes.2009.06.025 ↗
9. Phenomenology of BWR fuel assembly degradation10.1016/j.jnucmat.2017.12.004 ↗
10. Fission product release from trace irradiated UO2+x10.1016/S0022-3115(97)00350-4 ↗
11. Material release from the bundle in Phébus FP10.1016/j.anucene.2013.02.037 ↗
12. Recent advances in understanding ruthenium behaviour under air-ingress conditions during a PWR severe accident10.1016/j.pnucene.2009.09.011 ↗
13. Progress on ruthenium release and transport under air ingress conditions10.1016/j.nucengdes.2008.07.010 ↗
14. Source term of iodine and noble gas fission products in the fuel-to-sheath gap of intact operating nuclear fuel elements10.1016/0022-3115(90)90438-S ↗
15. Low volatile fission-product release and fuel volatilization during severe reactor accident conditions10.1016/S0022-3115(97)00292-4 ↗
16. Fission product release mechanisms during reactor accident conditions10.1016/S0022-3115(98)00738-7 ↗
17. Overview of experimental programs on core melt progression and fission product release behaviour10.1016/j.jnucmat.2008.07.005 ↗
18. Accelerating nuclear fuel development and qualification: Modeling and simulation integrated with separate-effects testing10.1016/j.jnucmat.2020.152267 ↗
19. Thermodynamics of Advanced Fuels - International Database (TAF-ID), Nuclear Energy Agency NEA. https://www.oecd-nea.org/jcms/pl_24703/thermodynamics-of-advanced-fuels-international-database-taf-id.
20. TAF-ID: an international thermodynamic database for nuclear fuels applications10.1016/j.calphad.2020.102212 ↗
21. Lukas · 2007
22. Thermodynamic investigations of fuel-cladding chemical interaction in U-5Fs and U-10Zr metallic fuels with the TAF-ID10.1016/j.jnucmat.2021.152981 ↗
23. Contribution to the study of fission products release from nuclear fuels in severe accident conditions: effect of the pO2 on Cs, Mo and Ba speciation10.1051/epjn/2019058 ↗
24. A study of the oxidation behaviour of FeCrAl-ODS in air and steam environments up to 1400°C10.1016/j.jnucmat.2020.152305 ↗
25. Simulation of the chemical state of high burnup (U,Pu)O2 fuel in fast reactors based on thermodynamic calculations10.1016/j.jnucmat.2019.151969 ↗
26. 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 ↗
27. Introïni · 2019
28. Thermochemically-informed mass transport model for interdiffusion of U and Zr in irradiated U-Pu-Zr fuel with fission products10.1016/j.jnucmat.2021.153089 ↗
29. Corrosion behaviour of AGR SIMFUELS10.1149/06617.0085ecst ↗
30. Hydrogen peroxide decomposition on simulated nuclear fuel bicarbonate/carbonate solutions10.1016/j.electacta.2020.135980 ↗
31. Fission product partitioning in aerosol release from simulated spent nuclear fuel10.1016/j.jnucmat.2015.06.002 ↗
32. Synthesis of simulated fuels containing CsI under gas-tight condition
33. Leaching of SIMFUEL in simulated granitic water: comparison to results in demineralized water10.1016/S0022-3115(96)00364-9 ↗
34. Oversby · 1999
35. The chemical effects of composition changes in irradiated oxide fuel materials II-Fission product segregation and chemical equilibria10.1016/0022-3115(76)90264-6 ↗
36. Le Gall · 2018
37. Geiger · 2016
38. Microstructural features of SIMFUEL - Simulated high-burnup U02-based nuclear fuel10.1016/0022-3115(91)90455-G ↗
39. MARS | French national synchrotron facility. https://www.synchrotron-soleil.fr/en/beamlines/mars.
40. ATHENA, ARTEMIS, HEPHAESTUS: data analysis for X-ray absorption spectroscopy using IFEFFIT10.1107/S0909049505012719 ↗
41. Measuring radioactive powder samples on the high-resolution powder diffraction beamline at the European synchrotron radiation facility10.1107/S0021889813003178 ↗
42. L. Lutterotti, MAUD - Material Analysis Using Diffraction, (n.d.). http://maud.radiographema.eu/.
43. Measurements of O/U ratio and oxygen potential for UO2+x (0≤x≲0.1)10.1080/18811248.1983.9733384 ↗
44. Phase equilibria in the quaternary molybdenum-ruthenium-rhodium-palladium system
45. The constitution of the uranium-palladium and uranium-rhodium-palladium systems
46. Phase equilibrium studies in the UO2-ZrO2 system10.1016/0022-1902(67)80205-7 ↗
47. Experimental studies and thermodynamic assessment of the Ba-Mo-O system by the CALPHAD method10.1016/j.jeurceramsoc.2021.01.010 ↗
48. Thermal expansions of NpO2 and some other actinide dioxides10.1016/S0022-3115(96)00750-7 ↗
49. High-temperature X-ray study of uranium oxides in the UO2-U3O8 region10.1016/0022-1902(55)80046-2 ↗
50. The X-ray thermal expansion of near-stoichiometric UO210.1016/0022-3115(66)90171-1 ↗
51. Thermodynamic study of hypostoichiometric urania10.1016/0022-3115(72)90053-0 ↗
52. On the relation between lattice parameter and O/M ratio for uranium dioxide-trivalent rare earth oxide solid solution10.1016/0022-3115(81)90544-4 ↗
53. Lattice parameter behavior with different Nd and O concentrations in (U1-yNdy)O2±x solid solution10.13182/NT14-136 ↗
54. Phase equilibria in the ternary URu3–URh3–UPd3 system10.1016/S0925-8388(98)00177-7 ↗
55. Wang · 2018