Accession Number : AD0782516

Title :   Fatigue Resistance of Type 348 Stainless Steel under Simulated Water Reactor Conditions.

Descriptive Note : Final rept.,

Corporate Author : NAVAL RESEARCH LAB WASHINGTON D C

Personal Author(s) : Smith,Hugh H. ; Shahinian,Paul

Report Date : 26 JUN 1974

Pagination or Media Count : 16

Abstract : The effects of neutron irradiation and high-temperature water-vapor environment on the fatigue behavior of Type 348 stainless steel were investigated. The tests were conducted in reverse bending at a constant amplitude of vibration in dry air, in water vapor, and in vacuum. Tests in water vapor were designed to simulate water-cooled reactor environments. Notched specimens were cycled at resonance, and crack-growth rates were determined by a method that relates changes in the frequency of vibration to crack growth. The general improvement in fatigue life for the irradiated condition was attributed mainly to decreased crack-growth rates. The fatigue life of this steel, when unirradiated, was longest in vacuum, was less in water vapor, and was least in air. The results of this study indicate that the fatigue performance of reactor components made of Type 348 stainless steel should not be adversely affected by the environment found in water-cooled reactors. (Modified author abstract)

Descriptors :   *Stainless steel, *Fatigue(Mechanics), *Radiation effects, Neutrons, Water vapor, Crack propagation, High temperature, Reactor materials

Subject Categories : Metallurgy and Metallography
      Fission Reactor Materials

Distribution Statement : APPROVED FOR PUBLIC RELEASE