journal article·2023-03Open access

Testing fast reactor fuels in a thermal reactor: Comparison of transmutation metallic fuel alloys behavior by scanning electron microscopy

Luca Capriotti, Fidelma G. Di Lemma, Jason M. Harp

Abstract

To optimize nuclear waste repository performance, the destruction of minor actinide elements, particularly Np and Am, in a neutron fast spectrum reactor is possible by incorporating these elements into nuclear fuel. Evaluating the performance of minor actinide containing fuel is of paramount importance to enabling this technology. However, such a task is challenging without an available domestic fast spectrum test reactor. A comparison of fuel performance tested in an available domestic thermal reactor at the Idaho National Laboratory, the Advanced Test Reactor, and in a fast spectrum reactor in France (Phénix) is presented in this study. This study evaluates the capability of using a cadmium shrouded test position to mimic the power profile along the fuel radius present in fast spectrum reactors so that thermally driven phenomenon (e.g., constituent redistribution) can be evaluated in a thermal reactor and determined to be prototypical of a fast reactor. Thus, optical microscopy and scanning electron microscopy has been performed on irradiated 35U-29Pu-4Am-2Np-30Zr fuel samples (where the number preceding the element is the weight percent concentration) from the two mentioned reactors that present similar irradiation temperatures and power conditions. The results indicate that fuel performance phenomena are reproducible in the two irradiation conditions. The redistribution of Zr occurred in the same manner for the two samples. Similar partitioning of U-Pu-Zr phases was observed, and the behavior of Am was similar in the analyzed specimens. Finally, the overall microstructure evolution seems not to be affected by minor actinides addition compared to expected behavior of conventional U-19Pu-10Zr ternary metal fuels for both specimens. Slight differences in fuel cladding chemical interaction were, however, observed. This difference is likely driven by difference in cladding composition rather than irradiation conditions.
Source: expertdata · Quality: candidate unverified · Source record ↗

Research context

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

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (31)

Show source-provided references
1. U.S. test plans for actinide transmutation fuel development
2. Report to congress on the advanced fuel cycle initiative: the future path for advanced spent fuel treatment and transmutation research, (2003).
3. Technology readiness levels for advanced nuclear fuels and materials development10.1016/j.nucengdes.2016.11.024 ↗
4. Cadmium Depletion Impacts on Hardening Neutron Spectrum for Advanced Fuel Testing in ATR
5. Hardening neutron spectrum for advanced actinide transmutation experiments in the ATR10.1093/rpd/nci167 ↗
6. Testing fast reactor fuels in a thermal reactor
7. J.M. Harp, S.L. Hayes, P.G. Medvedev, D.L. Porter, L. Capriotti, Testing Fast reactor fuels in a thermal reactor: a comparison report, Idaho Natl. Lab. Rep. (2017) INL/EXT-17-41677. 10.2172/1458766.10.2172/1458766 ↗
8. J.R. Kennedy, FUTURIX-FTA metal alloy fuel fabrication and characterization report, INL/EXT-07-12234. (2007).
9. Postirradiation Examination of FUTURIX-FTA metallic alloy experiments10.1016/j.jnucmat.2018.12.051 ↗
10. Postirradiation examination of AFC-1D, 1G, 1H, and 2A experiments
11. Metal fuel performance modeling and simulation10.1016/B978-0-12-803581-8.11676-5 ↗
12. Characterization of a minor actinides bearing metallic fuel pin irradiated in EBR-II
13. Metal fuel
14. Metallic fast reactor fuels10.1016/0149-1970(96)00005-4 ↗
15. Janney · 2018
16. Electron probe microanalysis of irradiated FUTURIX-FTA U-Pu-Zr alloy with added minor actinides10.1016/j.jnucmat.2019.151745 ↗
17. Constituent redistribution in U–Pu–Zr fuel during irradiation10.1016/j.jnucmat.2004.01.012 ↗
18. Irradiation behavior of metallic fast reactor fuels10.1016/0022-3115(92)90447-S ↗
19. Lanthanides in metallic nuclear fuels: their behavior and methods for their control10.1016/j.jnucmat.2011.08.036 ↗
20. Lanthanide migration and immobilization in metallic fuels10.1016/j.pnucene.2018.08.019 ↗
21. Reducing fuel-cladding chemical interaction: the effect of palladium on the reactivity of neodymium on iron in diffusion couples10.1016/j.jnucmat.2012.07.028 ↗
22. Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-910.1016/j.jnucmat.2017.07.040 ↗
23. Out-of-pile and postirradiated examination of lanthanide and lanthanide-palladium interactions for metallic fuel10.1016/j.jnucmat.2020.152727 ↗
24. Electron probe microanalysis of a METAPHIX UPuZr metallic alloy fuel irradiated to 7.0 at.% burn-up10.1016/j.jnucmat.2016.07.060 ↗
25. Reduction of FCCI effects in lanthanide–iron diffusion couples by doping with palladium10.1016/j.jnucmat.2013.04.060 ↗
26. Migration of minor actinides and lanthanides in fast reactor metallic fuel10.1016/j.jnucmat.2009.03.043 ↗
27. Metal fuel-cladding interaction10.1016/B978-0-08-056033-5.00067-7 ↗
28. Keiser · 2006
29. Investigation of fuel microstructure at the top of a metallic fuel pin after a reactor overpower transient10.1016/j.jnucmat.2020.152711 ↗
30. Preliminary studies on volatile fission gas distribution in minor actinide-bearing metal fuel
31. Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: a critical review10.1080/00295450.2017.1323535 ↗