IN-REACTOR FATIGUE TESTS OF A302-B STEEL REPRESENTING THE ELK RIVER REACTOR PRESSURE VESSEL,
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 n/sq 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)
Document Details
- Document Type
- Technical Report
- Publication Date
- Feb 15, 1965
- Accession Number
- AD0613053
Entities
People
- J. Russell Hawthorne
- Lendell E. Steele
Organizations
- United States Naval Research Laboratory