Spent fuel heatup following loss of water during storage. [PWR; BWR]
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.
- Publication Date:
- OSTI Identifier:
- Report Number(s):
- NUREG/CR-0649; SAND-77-1371
- DOE Contract Number:
- Resource Type:
- Technical Report
- Research Org:
- Sandia Labs., Albuquerque, NM (USA)
- Country of Publication:
- United States
- 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
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