IN-REACTOR STUDIES OF LOW CYCLE FATIGUE PROPERTIES OF A NUCLEAR PRESSURE VESSEL STEEL.
Abstract
An experimental irradiation assembly and associated instrumentation which have been developed and successfully utilized for the performance of dynamic in-reactor low cycle fatigue tests of reactor pressure vessel steels are described. The equipment provides for the simultaneous reverse bend testing of as many as fifteen sheet type specimens representing a range of strain amplitudes at controlled temperatures in the range 300 to 700F. The results of an exploratory investigation on the fatigue resistance of ASTM type A302-B steel during irradiation at 500F are presented and compared with data from out-of-reactor control tests. These preliminary data do not indicate any pronounced difference in the fatigue strength of irradiated versus unirradiated steel. Exploratory investigations are continuing. (Author)
Document Details
- Document Type
- Technical Report
- Publication Date
- Jul 27, 1964
- Accession Number
- AD0606773
Entities
People
- D. E. Steele
- J. Russell Hawthorne
Organizations
- United States Naval Research Laboratory