Response of spent LWR fuel to extreme environments

Conference · Wed Jan 01 04:00:00 EST 1986

OSTI ID:5720635

Sandoval, R P; Burian, R J; Kok, K D; DiSalvo, R; Balmert, M E; Freeman-Kelly, R; Fentiman, A W

The research reported in this paper addresses the radiological source term which could arise when irradiated fuel in transport from a commercial light water reactor is exposed to the extreme environments postulated for some transportation accidents, specifically those involving a fire. The release of spent fuel radionuclides to the environment requires a breach of both the cask and the fuel rod cladding. Past research has given significant emphasis to evaluating the response of the shipping cask to mechanical and/or thermal loads from hypothetical accidents. Less consideration has been given to evaluating the response of the fuel rods to these environments. In this paper, the response of the fuel rods to an extreme thermal event was experimentally evaluated and the quantity of solid fuel material that could be released from the fuel rods to the cask cavity was estimated. Briefly, the objectives of this study were as follows: (1) Identify those conditions within a transportation cask which might produce fuel-rod cladding failure, emphasizing conditions associated with fires, and (2) Determine by experiment and analysis the nature of the source term so produced. The release of radionuclides from coolant or deposits on the outer surfaces of the fuel assembly was not addressed in this study. 6 figs., 2 figs.

• Research Organization: Sandia National Labs., Albuquerque, NM (USA); Battelle Columbus Labs., OH (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 5720635
• Report Number(s): SAND-85-2208C; IAEA-SM-286/92; CONF-860604-23; ON: DE86011648
• Country of Publication: United States
• Language: English

Related Subjects

050900 -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420204* -- Engineering-- Shipping Containers
ACCIDENTS
AFTER-HEAT
BURNUP
CASKS
CONTAINERS
CREEP
ENERGY SOURCES
FAILURES
FIRES
FISSION PRODUCT RELEASE
FUELS
IAEA
INTERNATIONAL ORGANIZATIONS
MATERIALS
MECHANICAL PROPERTIES
NUCLEAR FUELS
PARTICLES
PARTICULATES
PERFORMANCE TESTING
REACTOR MATERIALS
REACTORS
RUPTURES
SOURCE TERMS
SPENT FUEL CASKS
SPENT FUELS
SWELLING
TEMPERATURE EFFECTS
TESTING
TRANSPORT
WATER COOLED REACTORS