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

Technical Report · Thu Mar 01 04:00:00 EST 1979

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

Benjamin, A S; McCloskey, D J; Powers, D A; Dupree, S A

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 Labs., Albuquerque, NM (USA)
• DOE Contract Number: EY-76-C-04-0789
• OSTI ID: 6272964
• Report Number(s): NUREG/CR-0649; SAND-77-1371
• Country of Publication: United States
• Language: English

Related Subjects

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
ACCIDENTS
AFTER-HEAT
BWR TYPE REACTORS
DESIGN
ENERGY TRANSFER
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL POOLS
HEAT TRANSFER
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SPENT FUEL ELEMENTS
SPENT FUEL STORAGE
WATER COOLED REACTORS
WATER MODERATED REACTORS