Hom, Brian M. | Engineering Papers

DOE OSTI2023

COBRA-SFS Version 6.2.1 User Guide: A Thermal Hydraulic Analysis Code for Spent Fuel Storage and Transportation Casks

This document is an updated and reduced version of the complete documentation of the COBRA-SFS thermal analysis code (COolant Boiling in Rod Arrays – Spent Fuel Storage) (Michener et al. 1995). This manual provides the analyst with input instructions and fundamental guidelines for contrasting models using COBRA-SFS. COBRA-SFS is designed to analyze the dry storage and transportation casks that house spent or used nuclear fuel. The primary focus and application is on square light water reactor fuel assemblies, however the code also has the capability to model hexagonal assemblies and is will suited to any geometry that can be defined as an extruded 2-D map.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

DOE OSTI2023

Devices and systems for material transportation

Various embodiments relate to devices for transporting high-assay low-enriched uranium (HALEU). A device may include at least one section, wherein each section of the at least one section includes a number of storage tubes. Each storage tube, which is configured to receive and hold a container, extends from adjacent a first end of the section toward a second, opposite end of the section. Each section further includes a number of flux traps, wherein each storage tube of the number of storage tubes is at least partially surrounded by a flux trap of the number of flux traps Associated systems are also disclosed.

Eidelpes, Elmar F.↗