Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

The contribution of spent-fuel shipping cask residual contamination to the transportation source term

Conference · · Transactions of the American Nuclear Society; (USA)
OSTI ID:5584657
; ; ; ;

The source term contribution from crud associated with spent-fuel assemblies was estimated. It was found that the population of spent-fuel rods as a function of adhered crud activity is bimodally distributed. Using the activity density mode corresponding to the majority of the fuel rod population for both BWR and PWR fuel rods transported in an NLI-1/2 cask gives a total adhered crud activity of {approx}2.2 Ci for a typical BWR two-assembly shipment and 7 Ci for a typical PWR one-assembly shipment. These values are generally much larger than those found for residual contamination. It is important to note, however, that data on inventories of crud are much more extensive than those for residual contamination. If the same particle size distribution is assumed for crud and cask residual contaminants, then aerosol attenuation for the two will be the same, and residual cask contamination will, therefore, generally be the less important source term contributor.

OSTI ID:
5584657
Report Number(s):
CONF-881011--
Journal Information:
Transactions of the American Nuclear Society; (USA), Journal Name: Transactions of the American Nuclear Society; (USA) Vol. 57; ISSN TANSA; ISSN 0003-018X
Country of Publication:
United States
Language:
English

Similar Records

A fuel response model for the design of spent fuel shipping casks
Conference · Sat Dec 31 23:00:00 EST 1988 · OSTI ID:6020112
A source-term method for determining spent-fuel transport cask containment requirements: Executive summary
Technical Report · Sun Jan 31 23:00:00 EST 1993 · OSTI ID:10141745
A source-term method for determining spent-fuel transport cask containment requirements: Executive summary
Technical Report · Sun Jan 31 23:00:00 EST 1993 · OSTI ID:6866921

Related Subjects

050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
42 ENGINEERING
420203 -- Engineering-- Handling Equipment & Procedures
ACCIDENTS
ACTIVITY LEVELS
AEROSOLS
BWR TYPE REACTORS
CASKS
COLLOIDS
CONTAINERS
CONTAMINATION
DESIGN
DISPERSIONS
DOSES
ENERGY SOURCES
FABRICATION
FUELS
LEAKS
MATERIALS
NUCLEAR FUELS
PWR TYPE REACTORS
RADIATION DOSES
REACTOR MATERIALS
REACTORS
REGULATIONS
RELIABILITY
SOLS
SOURCE TERMS
SPENT FUEL CASKS
SPENT FUELS
SURFACE CONTAMINATION
TRANSPORT
WATER COOLED REACTORS
WATER MODERATED REACTORS