Behavior of breached light water reactor spent fuel rods in air and inert atmospheres at 229/sup 0/C

Journal Article · Mon Apr 01 04:00:00 EST 1985 · Nucl. Technol.; (United States)

OSTI ID:6409990

Einziger, R E; Cook, J A

A whole-rod test was conducted at 229/sup 0/C to investigate the long-term stability of light water reactor spent fuel rods with artifically induced defects stored in inert and unlimited air atmospheres. Both boiling water reactor (BWR) and pressurized water reactor (PWR) rods were tested. After 2235 h, visual observations, diametral measurements, and radiographic smears were used to assess the degree of cladding deformation and particulate release. The same examinations plus metallography and x-ray analysis were conducted after 5962 h. Neither of the breached rods tested in inert atmosphere, nor the breached PWR rod tested in unlimited air, showed any measurable change from the pretest condition. The upper defect on the BWR rod tested in unlimited air had a 12.7-mm split after 2235 h and had 10% cladding deformation. The crack grew to 63.5 mm after 5962 h. X-ray analysis indicated that the UO/sub 2/ had oxidized to U/sub 3/O/sub 8/ at this defect. The difference in the behavior of the upper and lower defects is attributed to the accessibility of the air to the fuel due to the positioning of the defect with relation to the pellet/pellet interface.

• Research Organization: Westinghouse Hanford Company, Richland, Washington
• OSTI ID: 6409990
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 69:1; ISSN NUTYB
• Country of Publication: United States
• Language: English

Related Subjects

052002* -- Nuclear Fuels-- Waste Disposal & Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ACTINIDE COMPOUNDS
AIR
BWR TYPE REACTORS
CHALCOGENIDES
CRACKS
DEFECTS
DEFORMATION
DESTRUCTIVE TESTING
FISSION PRODUCT RELEASE
FLUIDS
FUEL ELEMENTS
FUEL-CLADDING INTERACTIONS
GASES
INDUSTRIAL RADIOGRAPHY
INERT ATMOSPHERE
MATERIALS TESTING
METALLOGRAPHY
OXIDES
OXYGEN COMPOUNDS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
SPENT FUEL ELEMENTS
SPENT FUEL STORAGE
STORAGE
TESTING
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
URANIUM OXIDES U3O8
WATER COOLED REACTORS
WATER MODERATED REACTORS
X-RAY RADIOGRAPHY