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Title: Spent fuel heatup following loss of water during storage. [PWR; BWR]

Technical Report ·
DOI:https://doi.org/10.2172/6272964· OSTI ID:6272964
; ; ;

An analysis of spent fuel heatup following a hypothetical accident involving drainage of the storage pool is presented. Computations based upon a new computer code called SFUEL have been performed to assess the effect of decay time, fuel element design, storage rack design, packing density, room ventilation, drainage level, and other variables on the heatup characteristics of the spent fuel and to predict the conditions under which clad failure will occur. Possible storage pool design modifications and/or onsite emergency action have also been considered.

Research Organization:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
DOE Contract Number:
EY-76-C-04-0789
OSTI ID:
6272964
Report Number(s):
NUREG/CR-0649; SAND-77-1371; TRN: 79-012847
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
FUEL POOLS
SPENT FUEL STORAGE
LOSS OF COOLANT
PWR TYPE REACTORS
AFTER-HEAT
HEAT TRANSFER
DESIGN
FUEL ELEMENT FAILURE
SPENT FUEL ELEMENTS
ACCIDENTS
ENERGY TRANSFER
FUEL ELEMENTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled