PNNL

2023

• Richmond D.J., B.M. Hom, B.J. Jensen, and C.L. Grant. 2023. COBRA-SFS Version 6.2.1 User Guide : A Thermal Hydraulic Analysis Code for Spent Fuel Storage and Transportation Casks. PNNL-33688. Richland, WA: Pacific Northwest National Laboratory. COBRA-SFS Version 6.2.1 User Guide : A Thermal Hydraulic Analysis Code for Spent Fuel Storage and Transportation Casks

2021

• Eidelpes E., B.M. Hom, R. Hall, H.E. Adkins, and J. Jarrell. 2021. "A High-Assay Low-Enriched Uranium Fuel Transportation Concept." Nuclear Science and Engineering 195, no. 3:279-299. PNNL-SA-156769. doi:10.1080/00295639.2020.1802161