journal article·2016-05

Modeling a failure criterion for U–Mo/Al dispersion fuel

Jae-Yong Oh, Yeon Soo Kim, Young-Wook Tahk, Hyun-Jung Kim, Eui-Hyun Kong, Jeong-Sik Yim

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Abstract

Abstract The breakaway swelling in U–Mo/Al dispersion fuel is known to be caused by large pore formation enhanced by interaction layer (IL) growth between fuel particles and Al matrix. In this study, a critical IL thickness was defined as a criterion for the formation of a large pore in U–Mo/Al dispersion fuel. Specifically, the critical IL thickness is given when two neighboring fuel particles come into contact with each other in the developed IL. The model was verified using the irradiation data from the RERTR tests and KOMO-4 test. The model application to full-sized sample irradiations such as IRISs, FUTURE, E-FUTURE, and AFIP-1 tests resulted in conservative predictions. The parametric study revealed that the fuel particle size and the homogeneity of the fuel particle distribution are influential for fuel performance.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Radioactive element chemistry and processing · Nuclear reactor physics and engineering

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References (25)

Show source-provided references
1. The United-States reduced enrichment research and test reactor (RERTR) program - Accomplishments, plans, and schedules
2. From high to low enriched uranium fuel in research reactors10.4028/www.scientific.net/AST.73.78 ↗
3. High density fuel development for research reactors
4. Observations on the irradiation behavior of U-Mo alloy dispersion fuel
5. Recent observations at the postirradiation examination of low-enriched U-Mo miniplates irradiated to high burnup
6. Post-irradiation examination of uranium–7 wt% molybdenum atomized dispersion fuel10.1016/j.jnucmat.2004.07.004 ↗
7. Kim · 2011
8. Amorphization of the interaction products in U-Mo/Al dispersion fuel during irradiation10.1016/j.jnucmat.2009.01.306 ↗
9. Transmission electron microscopy investigation of irradiated U–7 wt%Mo dispersion fuel10.1016/j.jnucmat.2007.12.006 ↗
10. Small angle neutron scattering by U-9% Mo/Al dispersion fuel irradiated to high burn-ups
11. Review of 15 years of high-density low-enriched UMo dispersion fuel development for research reactors in Europe10.5516/NET.07.2014.703 ↗
12. Analysis of fuel failures in experimental fuel U-Mo dispersion fuel plates
13. Influence of fuel-matrix interaction on the breakaway swelling of U-Mo dispersion fuel in Al10.5516/NET.07.2014.705 ↗
14. Modeling of interaction layer growth between U-Mo particles and an Al matrix10.5516/NET.07.2013.713 ↗
15. Irradiation-enhanced interdiffusion in the diffusion zone of U-Mo dispersion fuel in Al10.1007/BF02736563 ↗
16. Random close packing of disks and spheres in confined geometries10.1103/PhysRevE.80.051305 ↗
17. Full-sized plates irradiation with high UMo fuel loading - final results of Iris 1 experiment
18. Microstructural analysis of irradiated atomized U(Mo) dispersion fuel in an Al matrix with Si addition
19. Synthetic review of the IRIS3 experiment
20. UMo full size plate irradiation experiment IRIS-TUM – a progress report
21. Irradiation behavior of ground U(mo) fuel with and without Si added to the matrix10.1016/j.jnucmat.2011.02.002 ↗
22. Multi-physics simulation of the E-FUTURE-1 fuel, irradiation experiment
23. Fuel swelling and interaction layer formation in the SELENIUM Si and ZrN coated U(Mo) dispersion fuel plates irradiated at high power in BR210.1016/j.jnucmat.2014.12.073 ↗
24. Microstructural analysis of irradiated U-Mo fuel plates: recent results
25. Fission induced swelling of U-Mo/Al dispersion fuel10.1016/j.jnucmat.2015.06.006 ↗