Experimental studies of transient effects in fast reactor fuels.
Series I,
UO₂ irradiations /
by J. H. Field.

Description

Main Author

Field, J. H.

Related Names

General Electric Company. Atomic Power Equipment Department.
U.S. Atomic Energy Commission.

Language(s)

English

Published

Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1962.

Subjects

Uranium oxides.
Nuclear fuels > Nuclear fuels / Effect of radiation on.
Fast reactors.
Fast reactors.
Uranium oxides.
Nuclear fuels > Nuclear fuels / Effect of radiation on.

Summary

An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined, and the initial series of tests are described in some detail. Test results from five experiments in the TREAT reactor, using 1-in. OD SS-clad UO₂ fuel specimens, are compared with regard to fuel temperatures, mechanical integrity, and post-irradiation appearance. Incipient fuel pin failure limits for transients are identified with maximum fuel temperatures in the range of 7000 deg F. Multiple transient damage to the cladding is likely for transients above the melting point of the fuel.

Note

Work performed at the General Electric Company, Atomic Power Equipment Department, San Jose, California.
"GEAP-4130; Metals, Ceramics, and Materials."
"November 15, 1962."

Physical Description

74 pages : illustrations (some folded) ; 28 cm.

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