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First interim examination of defected BWR and PWR rods tested in unlimited air at 229/sup 0/C

Conference ·
OSTI ID:5799335
;
A five-year whole rod test was initiated to investigate the long-term stability of spent fuel rods under a variety of possible dry storage conditions. Both PWR and BWR rods were included in the test. The first interim examination was conducted after three months of testing to determine if there was any degradation in those defected rods stored in an unlimited air atmosphere. Visual observations, diametral measurements and radiographic smears were used to assess the degree of cladding deformation and particulate dispersal. The PWR rod showed no measurable change from the pre-test condition. The two original artificial defects had not changed in appearance and there was no diametral growth of the cladding. One of the defects in BWR rod showed significant deformation. There was approximately 10% cladding strain at the defect site and a small axial crack had formed. The fuel in the defect did not appear to be friable. The second defect showed no visible change and no cladding strain. Following examination, the test was continued at 230/sup 0/C. Another interim examination is planned during the summer of 1983. This paper discusses the details and meaning of the data from the first interim examination.
Research Organization:
Hanford Engineering Development Lab., Richland, WA (USA); EG and G Idaho, Inc., Idaho Falls (USA)
DOE Contract Number:
AC06-76FF02170
OSTI ID:
5799335
Report Number(s):
HEDL-SA-2848; CONF-830897-1; ON: DE83015474
Country of Publication:
United States
Language:
English

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Related Subjects

050900* -- Nuclear Fuels-- Transport
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11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
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BWR TYPE REACTORS
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FUEL ELEMENTS
HIGH TEMPERATURE
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
SPENT FUEL ELEMENTS
SPENT FUEL STORAGE
STABILITY
STORAGE
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS