journal article·2020-04

MOX fuel microstructural evolution during the VERDON-3 and 4 tests

C. Le Gall, S. Reboul, L. Fayette, T. Blay, I. Zacharie-Aubrun, I. Félines, K. Hanifi, I. Roure, P. Bienvenu, F. Audubert, Y. Pontillon, Jean-Louis Hazemann

Publisher page

Abstract

Abstract The VERDON-3 and -4 tests were part of the VERDON-ISTP programme that aimed at studying the fuel and fission products (FP) behaviour in severe accident conditions. The main objective of these two complementary tests was the study of MOX fuel behaviour and FP release under oxidising (VERDON-3) and reducing (VERDON-4) conditions at very high temperature (>2300 °C). Complementary to the on-line gamma spectrometry measurements performed during the two tests, post-test characterisations were carried out in order to tackle these tasks. The two samples recovered after the VERDON-3 and -4 tests were compared to a third one extracted from the same father rod and left as irradiated. This comparison enabled to highlight the effect of temperature and atmosphere on the fuel behaviour. These three samples were characterised by several techniques available at the LECA-STAR facility of the CEA Cadarache. Experimental observations showed that an interaction between the fuel and the cladding occurred in both types of conditions by interdiffusion mainly between U and Zr. This phenomenon led to the formation of a UyZr1-yO2±x cubic phase at the periphery of the fuel pellet which melted in the VERDON-4 test conditions, penetrating through the cracks of the sample and dissolving the fuel matrix. No liquid was formed during the VERDON-3 test despite the formation of a large fuel-cladding interaction zone.
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 (40)

Show source-provided references
1. Behaviour of fission products under severe PWR accident conditions VERCORS experimental programme—Part 1: general description of the programme10.1016/j.nucengdes.2009.06.028 ↗
2. Core loss during a severe accident (COLOSS)10.1016/j.nucengdes.2004.08.050 ↗
3. The HEVA experimental program10.13182/NT94-A35041 ↗
4. Chatelard · 2006 · 145
5. The UO2–ZrO2 system at high temperature (T > 2000 K): importance of the meta-stable phases under severe accident conditions10.1016/j.jnucmat.2005.04.052 ↗
6. Analysis of crystalline phases in core bore materials from three mile island unit 210.13182/NT89-A27643 ↗
7. Lessons learnt from VERCORS tests.: study of the active role played by UO2–ZrO2–FP interactions on irradiated fuel collapse temperature10.1016/j.jnucmat.2005.04.053 ↗
8. Overview of the VERDON-ISTP Program and main insights from the VERDON-2 air ingress test10.1016/j.anucene.2016.09.045 ↗
9. VERDON Laboratory : performances of the experimental LWR severe accident device and fisrt results of fission products release on high burn-up UO2 fuel
10. Le Gall · 2018
11. Contribution to the study of fission products release from nuclear fuels in severe accident conditions: effect of the pO2 on Cs, Mo and Ba speciation
12. Lemaignan · 2004
13. Olander · 2009 · vol. 1
14. Fission products and nuclear fuel behaviour under severe accident conditions part 1: main lessons learnt from the first VERDON test10.1016/j.jnucmat.2017.08.021 ↗
15. Thermo-Calc & DICTRA, computational tools for materials science10.1016/S0364-5916(02)00037-8 ↗
16. FIB/SEM examination of high burn-up UO2 in the center of a pellet10.1016/j.net.2017.12.002 ↗
17. A new shielded SIMS instrument for analysis of highly radioactive materials10.1016/S0169-4332(02)00789-4 ↗
18. Lattice parameter changes associated with the rim-structure formation in high burn-up UO2 fuels by micro X-ray diffraction10.1016/S0022-3115(00)00236-1 ↗
19. Detailed characterisations of high burn-up structures in oxide fuels10.1016/j.jnucmat.2007.04.037 ↗
20. Post-irradiation studies on LWR-MOX fuel fabricated by the optimized co-milling process10.1016/j.jnucmat.2003.10.004 ↗
21. Ciszak · 2017
22. Fission product speciation in the VERDON-3 and VERDON-4 MOX fuels samples
23. Fission product release and microstructure changes during laboratory annealing of a very high burn-up fuel specimen10.1016/j.jnucmat.2008.03.006 ↗
24. Fission product release and microstructure changes of irradiated MOX fuel at high temperatures10.1016/j.jnucmat.2013.09.022 ↗
25. Fission products and nuclear fuel behaviour under severe accident conditions part 2: fuel behaviour in the VERDON-1 sample10.1016/j.jnucmat.2017.08.002 ↗
26. E. Geiger · 2016
27. Sintering studies on UO2–PuO2 pellets with varying PuO2 content using dilatometry10.1016/S0022-3115(00)00394-9 ↗
28. Dependence upon oxygen potential of the interdiffusion in single crystalline UO2-(U, Pu)O210.1016/0167-2738(84)90150-4 ↗
29. Diffusion processes and surface effects in non-stoichiometric nuclear fuel oxides UO2+x and (U,Pu)O2+x10.1016/0022-3115(83)90249-0 ↗
30. Role of the O/U ratio on the sintering of UO210.1016/0022-3115(69)90170-6 ↗
31. Self-diffusion of uranium in UO210.1016/0022-3115(66)90138-3 ↗
32. Atomic transport properties in UO2 and mixed oxides (U, Pu)O210.1039/f29878301121 ↗
33. Fission product release under severe accidental conditions: general presentation of the program and synthesis of VERCORS 1–6 results10.1016/S0029-5493(01)00376-4 ↗
34. LWR severe accident simulation: synthesis of the results and interpretation of the first Phebus FP experiment FPT010.1016/S0029-5493(03)00157-2 ↗
35. Experimental interpretation and code validation based on the PHEBUS-FP programme: lessons learnt from the analysis of the containment scenario of FPT1 and FPT2 tests10.1016/j.nucengdes.2007.03.022 ↗
36. The objectives of the Phébus FP experimental programme and main findings10.1016/j.anucene.2013.03.037 ↗
37. 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 ↗
38. High temperature investigation of the solid/liquid transition in the PuO2–UO2–ZrO2 system10.1016/j.jnucmat.2015.10.007 ↗
39. Synthesis of the VERCORS experimental programme: separate-effect experiments on Fission Product release, in support of the PHEBUS-FP programme10.1016/j.anucene.2013.02.033 ↗
40. Assessment of solid/liquid equilibria in the (U, Zr)O2+y system10.1016/j.jnucmat.2017.07.045 ↗