Whole-rod testing of intact and defective LWR rods under expected dry-storage conditions

Conference · Wed Sep 01 04:00:00 EDT 1982

OSTI ID:6900739

Einziger, R E; Knecht, R L; Richardson, L; Cook, J

The objective of this project is to provide the Nuclear Regulatory Commission with information to confirm or establish spent fuel dry storage licensing positions relative to: (1) the long-term, low-temperature (less than 250/sup 0/C) behavior of spent fuel rods in dry storage; and (2) the radioactive contamination potential of crud from cladding in dry storage. The basic need for this data is to: confirm long-term, low temperature (less than 250/sup 0/C) spent fuel dry storage performance predictions based on theoretical analyses and on results from high-temperature, short-term laboratory tests; determine the nature and behavior of crud layers as a function of dry storage time; and determine the potential radioactive crud contamination (e.g., spalling characteristics) for dry storage. An eight-rod test matrix of PWR and BWR rods was chosen which consisted of all combinations of intact or breached cladding in an oxidizing or inert atmosphere. The PWR rods (30.5 GWD/MTU) were discharged from H.B. Robinson in May 1974, and the BWR rods (12.9 GWD/MTU) were discharged from Peach Bottom in March 1976. The eight test rods were visually inspected for crud and defects with the results recorded on video tape. Cladding penetration was confirmed. All the rods were put in test capsules with the appropriate atmosphere and leak checked. The test capsules were loaded into a test train and the train was placed in the furnace cavity. The test was started on September 15, 1982 and is presently at 230/sup 0/C. After the first 10-month run is completed, an interim examination, consisting of visual inspection, gamma scanning, and crud sampling, will be conducted.

• Research Organization: Westinghouse Hanford Co., Richland, WA (USA); Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 6900739
• Report Number(s): HEDL-SA-2769-FP; CONF-821037-41; ON: DE83004034
• Country of Publication: United States
• Language: English

Related Subjects

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11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Light-Water Moderated
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210200 -- Power Reactors
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BWR TYPE REACTORS
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FUEL ELEMENTS
LICENSING
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
SPENT FUEL ELEMENTS
SPENT FUEL STORAGE
STORAGE
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS