Published March 1979
| Version v1
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Spent fuel heatup following loss of water during storage
Description
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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A08/MF A01.Files
10480621.pdf
Files
(6.6 MB)
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Additional details
Additional titles
- Augmented title (English)
- PWR; BWR
Publishing Information
- Imprint Pagination
- 163 p.
- Report number
- NUREG/CR--0649
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10480621
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT; BWR TYPE REACTORS; FUEL ELEMENT FAILURE; FUEL STORAGE POOLS; HEAT TRANSFER; LOSS OF COOLANT; PWR TYPE REACTORS; SPECIFICATIONS; SPENT FUEL ELEMENTS; SPENT FUEL STORAGE
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; FUEL ELEMENTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; STORAGE; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- SAND--77-1371.