PNNL

2024

• Maheras S.J., A.B. Rigato, H.E. Adkins, D.R. Todd, K.I. Kaiser, S.T. Arm, and D.J. Richmond, et al. 2024. Technical Information Needs and Regulatory Considerations for Front-End Transportation Activities of HALEU Fuel Feed Material. PNNL-33999. Richland, WA: Pacific Northwest National Laboratory. Technical Information Needs and Regulatory Considerations for Front-End Transportation Activities of HALEU Fuel Feed Material
• Richmond D.J., K.M. Thomas, N.L. LaHaye, P.P. Lowry, J.B. Napier, S.M. Short, and D.R. Todd. 2024. Assessment of Technical Information Needs and Considerations for Front-End Activities for Molten Salt Fuel Types. PNNL-33899 Rev. 1. Richland, WA: Pacific Northwest National Laboratory. Assessment of Technical Information Needs and Considerations for Front-End Activities for Molten Salt Fuel Types

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

2022

• Richmond D.J., S.R. Suffield, J.A. Fort, and M.E. Higley. 2022. Uncertainty in Thermal Modeling of Spent Nuclear Fuel Casks. PNNL-33409. Richland, WA: Pacific Northwest National Laboratory. Uncertainty in Thermal Modeling of Spent Nuclear Fuel Casks

2021

• Grant C.L., C.F. Campbell, and D.J. Richmond. 2021. Sensitivity of Spent Fuel Temperatures to Variable Canister Backfills. PNNL-31875. Richland, WA: Pacific Northwest National Laboratory. Sensitivity of Spent Fuel Temperatures to Variable Canister Backfills
• Richmond D.J., J.A. Fort, and S.R. Suffield. 2021. "TRANSIENT THERMAL MODELING OF THE HIGH BURNUP DEMONSTRATION RESEARCH PROJECT CASK USING STAR-CCM+ AND COBRA-SFS." In Proceedings of the ASME Pressure Vessels and Piping Conference, (PVP 2021), July 13-15, 2021, Virtual, Online, 5, Paper No: PVP2021-62082, V005T07A031. New York, New York:ASME. PNNL-SA-150571. doi:10.1115/PVP2021-62082

2020

• Porter I.E., K.J. Geelhood, D.J. Richmond, D.V. Colameco, T.J. Zipperer, E.E. Torres, and W.G. Luscher, et al. 2020. FAST-1.0: Integral Assessment: Developed under NQA-1-2017. PNNL-29727. Richland, WA: Pacific Northwest National Laboratory. FAST-1.0: Integral Assessment: Developed under NQA-1-2017

2019

• Fort J.A., D.J. Richmond, B.J. Jensen, and S.R. Suffield. 2019. High-Burnup Demonstration: Thermal Modeling of TN-32B Vacuum Drying and ISFSI Transients. PNNL-29058. Richland, WA: Pacific Northwest National Laboratory. High-Burnup Demonstration: Thermal Modeling of TN-32B Vacuum Drying and ISFSI Transients

2018

• Richmond D.J., and K.J. Geelhood. 2018. "FRAPCON Analysis of Cladding Performance during Dry Storage Operations." Nuclear Engineering and Technology 50, no. 2:306-312. PNNL-SA-125967. doi:10.1016/j.net.2018.01.003