IRRADIATION EFFECTS IN THE EGCR FUEL

Journal Article · Sat Sep 01 04:00:00 EDT 1962 · Nuclear Sci. and Eng.

OSTI ID:4762646

Morgan, J G; Osborne, M F; Sisman, O

Post-irradiation examinations were completed on all but the very long burnup samples for the EGCR fuel evaluation studies. The results confirmed the reliability of this fuel element design at least up to the burnup thus far attained (2400 Mw-day/metric ton UO/sub 2/). Fission gas release was not excessive except for the very high temperature irradiations. Although the pellets did sometimes show considerable cracking, pieces did not fall into the central cavity, and the hollow cylinder pellet design was shown to be stable. In the 1600 deg F prototype experiments, ridges were formed in the clad at pellet interfaces and evidence of sigma phase formation and some void formation was found in the metallographic examination of the ridges. The CO/sup 2/ was found to contain many fine cracks which caused the pellets to break up on handling, but very little fuel shifting occurred before the cans were cut open. (auth)

• Research Organization: Oak Ridge National Lab., Tenn.
• NSA Number: NSA-17-002024
• OSTI ID: 4762646
• Journal Information: Nuclear Sci. and Eng., Journal Name: Nuclear Sci. and Eng. Vol. Vol: 14
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

BURNUP
CRACKS
CYLINDERS
DEFECTS
EGCR
FISSION PRODUCTS
FUEL CANS
FUEL ELEMENTS
FUELS
GASES
HIGH TEMPERATURE
IRRADIATION
METALLOGRAPHY
METALS, CERAMICS, AND OTHER MATERIALS
PELLETS
PLANNING
RADIATION EFFECTS
STABILITY
SURFACES
URANIUM DIOXIDE