Accession Number:

AD0613053

Title:

IN-REACTOR FATIGUE TESTS OF A302-B STEEL REPRESENTING THE ELK RIVER REACTOR PRESSURE VESSEL,

Descriptive Note:

Corporate Author:

NAVAL RESEARCH LAB WASHINGTON D C

Personal Author(s):

Report Date:

1965-02-15

Pagination or Media Count:

18.0

Abstract:

Dynamic low cycle fatigue tests of specimens from a 3-inch thick A302-B plate representative of the Elk River Reactor ERR pressure vessel have been performed inreactor at 550F. The test apparatus provided for the simultaneous testing of fifteen sheet-type specimens, representing five average strain amplitudes, in reverse bending. The total neutron dosage received by individual specimens at failure ranged from 7.6 to 8.8 x 10 to the 18th power nsq cm 1 Mev, as determined from iron and titanium dosimeter wires included in the experiment. The comparison of data derived from in-reactor tests and out-of-reactor control tests performed on duplicate equipment did not reveal an effect of irradiation on fatigue properties. Author

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Distribution Statement:

APPROVED FOR PUBLIC RELEASE