FURTHER RESULTS OF IRRADIATION OF URANIUM CARBIDE

Journal Article · Mon May 01 00:00:00 EDT 1961 · Nuclear Sci. and Eng.

OSTI ID:4063338

Hare, A W; Alfant, S; Rough, F A; Sinizer, D I

The results of postirradiation examinations on UC compounds having nominal compositions of 4.6, 4.8, snd 5.0 wt.% C are given after irradiation to approximate burnups of from 1000 to 15,000 Mwd/t of U. Density changes are small, varying from a minimum of 0.7% to a maximum of about 2.5%. Cracking occurs in all specimens; however, it can probably be largely attributed to thermal stresses. Depletion of carbon occurs in the specimens having the nominal 5 wt.% C composition. Metallographic examination shows that these specimens appear to revert to the 4.8 wt.% C stoichiometric composition. The fission gas retention properties of this material appear quite good. In all cases, the amount of fission gas released is comparable to the calculated amount released by recoil. (auth)

• Research Organization: Battelle Memorial Inst., Columbus, Ohio
• NSA Number: NSA-15-019964
• OSTI ID: 4063338
• Journal Information: Nuclear Sci. and Eng., Journal Name: Nuclear Sci. and Eng. Vol. Vol: 10
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

ADSORPTION
BURNUP
CARBON
CRACKS
DECOMPOSITION
DENSITY
FISSION PRODUCTS
GASES
IRRADIATION
LOSSES
METALLOGRAPHY
METALS, CERAMICS, AND OTHER MATERIALS
RADIATION EFFECTS
TESTING
THERMAL STRESSES
URANIUM CARBIDES
VARIATIONS