Accession Number : ADA089697


Title :   A Review of Fatigue Crack Growth of Pressure Vessel and Piping Steels in High-Temperature, Pressurized Reactor-Grade Water.


Descriptive Note : Memorandum rept.,


Corporate Author : NAVAL RESEARCH LAB WASHINGTON DC


Personal Author(s) : Cullen,W H ; Torronen,Kari


Full Text : https://apps.dtic.mil/dtic/tr/fulltext/u2/a089697.pdf


Report Date : 19 Sep 1980


Pagination or Media Count : 128


Abstract : Fatigue crack growth data sets, for pressure vessel and piping steels, in reactor-grade water environment have appeared in various reports and publications since about 1972. All of the results which have been published from 1972 through 1979 have been plotted and are presented in this report. Beginning with a discussion of the need for these data, and an explanation of the laboratory facilities which are required for this research, this report goes on to describe the overall trends which have evolved through consideration of the data sets and the conditions under which they were generated. A model for hydrogen assisted fatigue crack growth is described and applied to the pressurized water reactor type of environment. A complete listing of references is included in the report. (Author)


Descriptors :   *STEEL , *PIPES , *CRACK PROPAGATION , *PRESSURE VESSELS , *NUCLEAR REACTORS , PREDICTIONS , MODELS , WATER , HIGH TEMPERATURE , HIGH PRESSURE , FRACTOGRAPHY , DATA ACQUISITION , FATIGUE(MECHANICS) , HYDROGEN EMBRITTLEMENT , SET THEORY , GRAPHIC ARTS


Subject Categories : Metallurgy and Metallography
      Structural Engineering and Building Technology
      Mechanics


Distribution Statement : APPROVED FOR PUBLIC RELEASE