Status of rod consolidation
Two of the factors that need to be taken into account with rod consolidation are (1) the effects on rods from their removal from the fuel assembly and (2) the effects on rods as a result of the consolidation process. Potential components of both factors are described in the report. Discussed under (1) are scratches on the fuel rod surfaces, rod breakage, crud, extended burnup, and possible cladding embrittlement due to hydrogen injection at BWRs. Discussed under (2) are the increased water temperature (less than 10/sup 0/C) because of closer packing of the rods, formation of crevices between rods in the close-packed mode, contact with dissimilar metals, and the potential for rapid heating of fuel rods following the loss of water from a spent fuel storage pool. Another factor that plays an important role in rod consolidation is the cost of disposal of the nonfuel-bearing components of the fuel assembly. Also, the dose rate from the components - especially Inconel spacer grids - can affect the handling procedures. Several licensing issues that exist are described. A list of recommendations is provided. 98 refs., 5 figs., 5 tabs.
- Research Organization:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5807117
- Report Number(s):
- PNL-5122; ON: DE85013030
- Country of Publication:
- United States
- Language:
- English
Similar Records
Rod consolidation of RG and E's (Rochester Gas and Electric Corporation) spent PWR (pressurized water reactor) fuel
Status of rod consolidation, 1988
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
FUEL CYCLE
FUEL RACKS
CONFIGURATION
PWR TYPE REACTORS
SPENT FUEL STORAGE
FEASIBILITY STUDIES
LICENSING
DEFECTS
DRY STORAGE
FUEL ASSEMBLY DISMANTLING
INTERGRANULAR CORROSION
OXIDES
STRESS CORROSION
CHALCOGENIDES
CHEMICAL REACTIONS
CORROSION
MECHANICAL STRUCTURES
OXYGEN COMPOUNDS
REACTORS
STORAGE
SUPPORTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
050900* - Nuclear Fuels- Transport
Handling
& Storage
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled