Author: G. GabettaPublisher:
ISBN:
Category : Nuclear pressure vessels
Languages : en
Pages : 26
Book Description
Fractographic and Microstructural Analysis of Fatigue Specimens of A302 Grade B Steel Tested in Air at Room Temperature
Author: G. GabettaPublisher:
ISBN:
Category : Nuclear pressure vessels
Languages : en
Pages : 26
Book Description
Alloys Index
Author: Monthly Catalog of United States Government Publications
Author: R & D Abstracts
Author: Technology Reports Centre (Great Britain)Publisher:
ISBN:
Category :
Languages : en
Pages : 620
Book Description
A Review of Fatigue Crack Growth of Pressure Vessel and Piping Steels in High-temperature, Pressurized Reactor-grade Water
Author: W. H. CullenPublisher:
ISBN:
Category : Fractography
Languages : en
Pages : 134
Book Description
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).
INIS Atomindex
Author: Technical Abstract Bulletin
Author: Government reports annual index
Author: Metals Abstracts
Author: Regulatory and Technical Reports
Author: U.S. Nuclear Regulatory Commission. Policy and Publications Management BranchPublisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 380
Book Description