Monolithic, plate-type fuels are the proposed fuel form for the conversion of the research and test reactors to achieve higher uranium densities within the reactor core. This fuel type is comprised of a low enrichment, a high density U-10Mo alloy fuel-foil, which is sandwiched between diffusion barriers and encapsulated in a cladding material. To understand the irradiation performance, fuel-plates are being benchmarked for large number of parameters. In this work, effects of the cladding material were studied. In particular, a monolithic fuel-plate with U7Mo foil and Zry-4 cladding was simulated to explore feasibility of using Zircaloy as a surrogate cladding material. For this, a selected mini-plate from RERTR-7 tests was simulated first with as-run irradiation history. By using same irradiation parameters, a second case, a plate with U10Mo fuel and Al6061 cladding was simulated to make a comparative assessment. The results indicated that the plate with Zircaloy cladding would operate roughly 50 °C hotter compared with the plate with Aluminum cladding. Larger displacement profiles along the thickness for the plate with Zircaloy cladding were observed. Higher plastic strains occur for the plate with Aluminum cladding. The results have revealed that any pre-irradiation stresses would be relieved relatively fast in reactor and the fuel-foil would be essentially stress-free during irradiation. The fuel stresses however, develop at reactor shutdown. The plate with Zircaloy cladding would have higher residual stresses due to higher pre-shutdown temperatures. Similarly, the stresses magnitudes are higher in the foil core for the plates with Zircaloy cladding. Finally, pressure on the fuel is significantly higher for the plates with Zircaloy cladding. Overall, employing a Zircaloy as surrogate cladding material did not provide a better thermo-mechanical performance compared with the Aluminum cladding.
Skip Nav Destination
2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5001-5
PROCEEDINGS PAPER
Effects of Cladding Material on Irradiation Performance of Monolithic Mini-Plates
Hakan Ozaltun
Hakan Ozaltun
Idaho National Laboratory, Idaho Falls, ID
Search for other works by this author on:
Hakan Ozaltun
Idaho National Laboratory, Idaho Falls, ID
Paper No:
ICONE24-60120, V001T02A009; 12 pages
Published Online:
October 25, 2016
Citation
Ozaltun, H. "Effects of Cladding Material on Irradiation Performance of Monolithic Mini-Plates." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Charlotte, North Carolina, USA. June 26–30, 2016. V001T02A009. ASME. https://doi.org/10.1115/ICONE24-60120
Download citation file:
17
Views
Related Proceedings Papers
Related Articles
EBR-II Metallic Driver Fuel—A Live Option
J. Eng. Power (October,1981)
Effects of the Foil Flatness on Irradiation Performance of U10Mo Monolithic Mini-Plates
ASME J of Nuclear Rad Sci (October,2015)
Related Chapters
Dissolution and Hydrogen Diffusion Control of IGSCC in Sensitized Aluminum-Magnesium Alloys
International Hydrogen Conference (IHC 2012): Hydrogen-Materials Interactions
Layer Arrangement Impact on the Electromechanical Performance of a Five-Layer Multifunctional Smart Sandwich Plate
Advanced Multifunctional Lightweight Aerostructures: Design, Development, and Implementation
Structural Performance of Thermo-Active Foundations
Thermoactive Foundations for Sustainable Buildings