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3D Printing Possibilities: Additive Manufacturing Impact Limiters for Transportation Casks
With the significant advances in additive manufacturing (AM), otherwise known as 3D printing, Orano Federal Services and the University of North Carolina at Charlotte recently re-examined the capabilities to print impact limiters for transportation casks used to ship spent nuclear fuel. Impact limiters protect transportation casks (sometimes also referred to as transportation overpacks) and their contents during an accident. Impact limiter designs must withstand testing based on a certain significance level of hypothetical accidents, including drops, crushing, fires, and immersion in water.
Benjamin R. Betzler, David Chandler, Eva E. Davidson (née Sunny), Germina Ilas
Nuclear Science and Engineering | Volume 187 | Number 1 | July 2017 | Pages 81-99
Technical Paper | doi.org/10.1080/00295639.2017.1292090
Articles are hosted by Taylor and Francis Online.
A high-fidelity model of the High Flux Isotope Reactor (HFIR) with a low-enriched uranium (LEU) fuel design and a representative experiment loading has been developed to serve as a new reference model for LEU conversion studies. With the exception of the fuel elements, this HFIR LEU model is completely consistent with the current highly enriched uranium HFIR model. Results obtained with the new LEU model provide a baseline for analysis of alternate LEU fuel designs and further optimization studies.
The newly developed HFIR LEU model has an explicit representation of the HFIR-specific involute fuel plate geometry, including the within-plate fuel meat contouring, and a detailed geometry model of the fuel element side plates. Such high-fidelity models are necessary to accurately account for the self-shielding from 238U and the depletion of absorber materials present in the side plates. In addition, a method was developed to account for fuel swelling in the high-density LEU fuel plates during the depletion simulation. Calculated time-dependent metrics for the HFIR LEU model include fission rate and cumulative fission density distributions, flux and reaction rates for relevant experiment locations, point kinetics data, and reactivity coefficients.