Assessment of Existing Transportation Packages for Use with HALEU

Extended Enrichment Accident Tolerant LWR Fuel Isotopic and Lattice Parameter Trends

“…Transportation of UO2 enriched to > 5 wt % 235 U has previously been investigated, but without specific consideration of ATF designs. [Hall et al 2020]. Two transportation packages reviewed are relevant to BWR ATF transportation-the Framatome TN-B1 (BWR pellets, rods, and fuel assemblies) and the CHT-OP-TU (BWR pellets).…”

Analysis of the 30B UF₆ Container for Use with Increased Enrichment

“…Likewise, the UX30 SARP [7] does not provide sample inputs. The models for this evaluation were based on the HAC models developed for ORNL's Assessment of Existing Transportation Packages for Use with HALEU (ORNL/TM-2020/1725) [1]. Key aspects of the models include:…”

“…For comparison, the 1x1 arrays with the 0.6 cm thick water film thickness were analyzed with no HUR present, with HUR present, and with the HUR present with the spherical HF shell around the HUR (similar to the DN-30 analysis [8] and the ORNL assessment [1]). The results shown in Table demonstrate the importance of the HUR and the HF (impurities) configuration to the system.…”

“…These advancements will necessitate the ability to transport LEU+ and HALEU fuel materials. Assessment of Existing Transportation Packages for Use with HALEU (ORNL/TM-2020/1725[1]) assesses the potential to use currently licensed transportation packages for the transportation of HALEU by evaluating a representative package for each uranium fuel form category (for example, oxide and/or metal in fuel assemblies, fuel pins, powder, pellets, and uranium hexafluoride [UF6].) This report expands on the UF6 analysis.…”

“…GAIN's primary objective is to provide the nuclear industry and entrepreneurs with a single point of access to the national laboratory system and its expertise and research tools. This study was performed in collaboration with representatives from the Nuclear Energy Institute (NEI) and the US Nuclear Regulatory Commission (NRC).The UF6 study described in the ORNL assessment[1] evaluated the DN-30 package[2,3]. The primary objectives of this effort were to determine whether the existing package design could be used to transport (and store) 30B cylinders containing UF6 in the LEU+ and HALEU enrichment range, what limitations might be required (i.e., smaller maximum transportation array size), and whether adequate applicable benchmark critical experiments could be identified for computer code validation.…”