Arrival condition of spent fuel after storage, handling, and transportation

Technical Report · Sun Oct 31 23:00:00 EST 1982

DOI:https://doi.org/10.2172/6726336· OSTI ID:6726336

Bailey, W J; Pankaskie, P J; Langstaff, D C; Gilbert, E R; Rising, K H; Schreiber, R E

This report presents the results of a study conducted to determine the probable arrival condition of spent light-water reactor (LWR) fuel after handling and interim storage in spent fuel storage pools and subsequent handling and accident-free transport operations under normal or slightly abnormal conditions. The objective of this study was to provide information on the expected condition of spent LWR fuel upon arrival at interim storage or fuel reprocessing facilities or at disposal facilities if the fuel is declared a waste. Results of a literature survey and data evaluation effort are discussed. Preliminary threshold limits for storing, handling, and transporting unconsolidated spent LWR fuel are presented. The difficulty in trying to anticipate the amount of corrosion products (crud) that may be on spent fuel in future shipments is also discussed, and potential areas for future work are listed. 95 references, 3 figures, 17 tables.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6726336
• Report Number(s): PNL-3582; TTC-0165; ON: DE83002634
• Country of Publication: United States
• Language: English

Related Subjects

050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
CORROSION PRODUCTS
DAMAGE
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL ELEMENTS
MATERIALS HANDLING
REACTOR COMPONENTS
REACTORS
SPENT FUEL ELEMENTS
SPENT FUEL STORAGE
STORAGE
TRANSPORT
WATER COOLED REACTORS