Characterization of LWR spent-fuel rods used in the NRC low-temperature whole rod and crud performance test
- comps.
Westinghouse Hanford Company (WHC) and EG and G-Idaho are conducting a joint evaluation for the Nuclear Regulatory Commisssion (NRC) to provide information in establishing licensing positions relative to long-term, low-temperature performance of spent fuel rods in dry storage and potential crud contamination for the dry storage cycle. The evaluation will establish the spent fuel performance of intact and defected light water reactor (LWR) fuel rods under inert and unlimited air environments. The four H.B. Robinson Unit 2 pressurized water reactor (PWR) fuel rods and four Peach Bottom-II boiling water reactor (BWR) spent fuel rods will be placed in a whole rod test furnace at a temperature between 230 and 245 deg C for a total of 50 months. Interim and final examinations are planned to assess behavior during the test. A literature search was conducted, and available nondestructive, metallographic, and fission gas data were compiled to provide a basis for selection of actual test rods and a description of the initial spent fuel test rod condition. The H.B. Robinson Unit 2 PWR fuel rods have been well characterized from other programs. The Peach Bottom-II BWR fuel rods are not as well characterized; however, eddy current examinations have been conducted on all the test rods. The visual examinations and crud characterization information to be gathered as part of the pretest rod characterization will be reported in mid-FY 1983. 29 figures, 19 tables.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (United States)
- Sponsoring Organization:
- USNRC
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 7015733
- Report Number(s):
- NUREG/CR--2871; HEDL-TME-82-27; ON: DE83002133
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
BWR TYPE REACTORS
ENRICHED URANIUM REACTORS
FISSION PRODUCT RELEASE
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
FUEL SCANNING
GAMMA FUEL SCANNING
GAMMA RADIOGRAPHY
INDUSTRIAL RADIOGRAPHY
MATERIALS TESTING
NONDESTRUCTIVE TESTING
PEACH BOTTOM-2 REACTOR
PERFORMANCE TESTING
PLANNING
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
ROBINSON-2 REACTOR
SPENT FUEL ELEMENTS
SPENT FUEL STORAGE
STORAGE
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
BWR TYPE REACTORS
ENRICHED URANIUM REACTORS
FISSION PRODUCT RELEASE
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
FUEL SCANNING
GAMMA FUEL SCANNING
GAMMA RADIOGRAPHY
INDUSTRIAL RADIOGRAPHY
MATERIALS TESTING
NONDESTRUCTIVE TESTING
PEACH BOTTOM-2 REACTOR
PERFORMANCE TESTING
PLANNING
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
ROBINSON-2 REACTOR
SPENT FUEL ELEMENTS
SPENT FUEL STORAGE
STORAGE
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS