journal article·2026-01

Post-irradiation examinations on a fast reactor MOX fuel pin with high Pu content irradiated at high burnup in PHENIX

L. Fayette, N. Chauvin, J. Lamontagne, V. Blanc, F. Martin, S. Reboul, N. Robert, I. Zacharie-Aubrun, T. Blay, K. Hanifi, I. Roure, P. Bienvenu, J. Noirot

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OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies

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References (33)

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1. High plutonium content oxide fuel for Pu burning in fast reactors. CAPRA irradiation programme and first in pile experimental results
2. Loi n° 91-1381 du 30 décembre 1991 relative aux recherches sur la gestion des déchets radioactifs, 1991. https://www.legifrance.gouv.fr/jorf/id/JORFTEXT000000356548 (accessed December 16, 2024).
3. IAEA-TECDOC-876, progress in liquid metal fast reactor technology
4. Development of fast reactor fuel for plutonium burning irradiation programme
5. First In-pile experimental results of high-plutonium-content oxide fuel for plutonium burning in fast reactors
6. Plutonium Management for More Agility | PUMMA Project | Fact Sheet | H2020, CORDIS Eur. Comm. (n.d.). https://cordis.europa.eu/project/id/945022 (accessed March 18, 2025).
7. Properties of mixed oxide with high plutonium content as a function of their fabrication route
8. PuMMA blind benchmark: performance of high plutonium content MOX fuel under irradiation10.1016/j.nucengdes.2025.113960 ↗
9. Post-irradiation examinations and high-temperature tests on undoped large-grain UO2 discs10.1016/j.jnucmat.2015.03.008 ↗
10. GERMINAL, a fuel performance code of the PLEIADES platform to simulate the in-pile behaviour of mixed oxide fuel pins for sodium-cooled fast reactors10.1016/j.jnucmat.2018.12.030 ↗
11. Chapter 9 - two fuel performance codes of the PLEIADES platform: ALCYONE and GERMINAL
12. TRIPOLI-4®, CEA, EDF and AREVA reference Monte Carlo code, jt. Int. Conf. Supercomput. Nucl. Appl. Monte Carlo 2013 SNA MC 2013 Pluri- Trans-discip. New model
13. New capabilities of analyses with a versatile nuclearized dual beam
14. Determination of the pressure in micrometric bubbles in irradiated nuclear fuels10.1016/j.jnucmat.2020.152591 ↗
15. Restructuring in high burn-up UO2 fuels: experimental characterization by electron backscattered diffraction10.1063/5.0104865 ↗
16. Renewal of the shielded Electron Probe Microanalyser (EPMA) in the CEA LECA-STAR hot laboratory: safety and technical improvements
17. Bienvenu · 2024
18. Fiji: an open-source platform for biological-image analysis10.1038/nmeth.2019 ↗
19. Detailed characterisations of high burn-up structures in oxide fuels10.1016/j.jnucmat.2007.04.037 ↗
20. Change of fuel-to-cladding gap width with the burn-up in FBR MOX fuel irradiated to high burn-up10.1016/j.jnucmat.2004.01.003 ↗
21. Microstructural characterization of high burn-up mixed oxide fast reactor fuel10.1016/j.jnucmat.2013.05.067 ↗
22. Modeling high burnup structure in oxide fuels for application to fuel performance codes. Part I: high burnup structure formation10.1016/j.jnucmat.2020.152296 ↗
23. Development of fuel performance analysis code, BISON for MOX, named Okami: analyses of pore migration behavior to affect the MA-bearing MOX fuel restructuring10.1016/j.jnucmat.2021.153038 ↗
24. Fuel performance of fast spectrum oxide Fuel
25. Comparison of the radial effects of burnup on fast reactor MOX fuel microstructure and solid fission products10.1016/j.jnucmat.2020.152003 ↗
26. Irradiation performance of PFBR MOX fuel after 112GWd/t burn-up10.1016/j.jnucmat.2014.01.045 ↗
27. PuMMA blind benchmark on high Pu content MOX fuel irradiation, Submitt10.1016/j.nucengdes.2025.113960 ↗
28. Fission product speciation across a UO2 spent nuclear fuel10.1016/j.jnucmat.2023.154660 ↗
29. Actinide redistribution due to pore migration in hypostoichiometric mixed-oxide fuel pins10.1016/0022-3115(75)90253-6 ↗
30. Distributions of volatile fission products in or near the fuel-cladding gap of the FBR MOX fuel pins irradiated to high burn-up
31. Fission product behaviour in phenix fuel pins at high burnup10.1016/0022-3115(92)90453-R ↗
32. Electron microscopy characterization of fast reactor MOX Joint Oxyde-Gaine (JOG)10.1016/j.jnucmat.2019.151964 ↗
33. Effects of irradiation on the insolubility of sodium fast reactor (U,Pu)O2 mixed oxide with a very high amount of plutonium10.1016/j.jnucmat.2023.154727 ↗