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

Technical Report · Tue Oct 31 00:00:00 EDT 2023

DOI:https://doi.org/10.2172/2326087· OSTI ID:2326087

Richmond, David J. ^[1]; Hom, Brian M. ^[1]; Jensen, Ben J. ^[1]; Grant, Christopher L. ^[1]

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1. Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

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.

• Research Organization: Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-76RL01830
• OSTI ID: 2326087
• Report Number(s): PNNL-33688
• Country of Publication: United States
• Language: English