Technical description of the NRC long-term whole-rod and crud performance test
Westinghouse Hanford Company (WHC) and EG and G-Idaho are jointly conducting a long-term, low-temperature, spent-fuel, whole rod and crud behavior test to provide the Nuclear Regulatory Commission (NRC) with information to assist in the licensing of light water reactor (LWR) spent-fuel, dry storage facilities. Readily available fuel rods from an H.B. Robinson Unit 2 (PWR) fuel assembly and a Peach Bottom-II (BWR) fuel assembly were selected for use in the 50-month test. Both intact and defected rods will be tested in inert and oxidizing atmospheres. A 230/sup 0/C test temperature was selected for the first 10-month run. Both nondestructive and destructive examinations are planned to characterize the fuel rod behavior during the 5-y test. Four interim examinations and a final examination will be conducted. Crud spallation behavior will be investigated by sampling the crud particulate from the test capsules at each of the four interim examinations and at the end of the test. The background to whole rod testing, description of rod breach mechanisms, and a detailed description of the test are presented in this document.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 6726374
- Report Number(s):
- NUREG/CR-2889; HEDL-TME-82-32; ON: DE83001593
- Country of Publication:
- United States
- Language:
- English
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Wed Sep 01 00:00:00 EDT 1982
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OSTI ID:7015733
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Related Subjects
050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CONTAMINATION
ENRICHED URANIUM REACTORS
EQUIPMENT
FOULING
FUEL ASSEMBLIES
FUEL CANS
FUEL ELEMENTS
FUEL RODS
HOT CELLS
LABORATORY EQUIPMENT
LEAKS
OXIDATION
PEACH BOTTOM-2 REACTOR
PERFORMANCE TESTING
PLANNING
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
ROBINSON-2 REACTOR
SPECIFICATIONS
SPENT FUEL ELEMENTS
SPENT FUEL STORAGE
STORAGE
TESTING
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WEIGHT MEASUREMENT
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CONTAMINATION
ENRICHED URANIUM REACTORS
EQUIPMENT
FOULING
FUEL ASSEMBLIES
FUEL CANS
FUEL ELEMENTS
FUEL RODS
HOT CELLS
LABORATORY EQUIPMENT
LEAKS
OXIDATION
PEACH BOTTOM-2 REACTOR
PERFORMANCE TESTING
PLANNING
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
ROBINSON-2 REACTOR
SPECIFICATIONS
SPENT FUEL ELEMENTS
SPENT FUEL STORAGE
STORAGE
TESTING
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WEIGHT MEASUREMENT
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS