In-Reactor Studies of Low-Cycle Fatigue Properties of a Nuclear Pressure Vessel Steel

Autor: L.E. Steele, J.R. Hawthorne
Rok vydání: 2009
Předmět:
DOI: 10.1520/stp43539s
Popis: 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)
Databáze: OpenAIRE