First Post Irradiation Examinations on a fast reactor grade MOX fuel (U0.6,Pu0.4)O2 for Pu-burning application, irradiated in the High Flux Reactor
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OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Radioactive element chemistry and processing
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References (17)
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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. Euratom H2020 PuMMA project (grant no. 945022); https://pumma-h2020.eu/, 2023.
3. SNETP https://snetp.eu/wp-content/uploads/2023/09/ESNII_Vision_Paper_2022.pdf, 2022.
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5. Fuel cycle strategies and plutonium management in Europe10.1016/j.pnucene.2007.09.001 ↗
6. Presentation of the new European project PuMMA devoted to plutonium management in the whole fuel cycle
7. Towards design guidelines for fast reactor oxide fuel pins with high Pu content: driving post irradiation examination by benchmarking European fuel performance codes
8. Euratom 7th Framework Programme (FP7) ESNII+, grant no 605172; https://cordis.europa.eu/project/id/605172, 2013.
9. C. Fuchs et al., Project CAPRA: fabrication of 3 fuel pins TRABANT2 for irradiation in HFR-Petten, JRC technical note K 02 98 192, 3-November 1998.
10. NIH image to ImageJ: 25 years of image analysis10.1038/nmeth.2089 ↗
11. Thermal conductivity of (U, Pu) O2−x mixed oxide fuel10.1016/0022-3115(92)90470-6 ↗
12. Thermal properties of UO2 and MOX10.1016/B978-0-08-056033-5.00038-0 ↗
13. Bailly · 1999
14. 2.03-Fuel performance of fast spectrum oxide Fuel10.1016/B978-0-12-803581-8.11690-X ↗
15. A review of microstructural features in fast reactor mixed oxide fuels10.1016/j.jnucmat.2018.05.076 ↗
16. Radial microstructural evolution in low burnup fast reactor MOX fuel10.1016/j.jnucmat.2019.06.009 ↗
17. Post-irradiation examinations of annular mixed oxide fuels with average burnup 4 and 5% FIMA10.1016/j.jnucmat.2020.152076 ↗