Author: W. H. Cullen
Publisher:
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).
A Review of Fatigue Crack Growth of Pressure Vessel and Piping Steels in High-temperature, Pressurized Reactor-grade Water
Author: W. H. Cullen
Publisher:
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).
Publisher:
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).
NUREG/CR.
Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 518
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 518
Book Description
Environmentally Assisted Cracking
Author: W. Barry Lisagor
Publisher: ASTM International
ISBN: 0803112769
Category : Alloys
Languages : en
Pages : 540
Book Description
Papers included topics of phenomena, basic mechanisms, modeling, test methodologies, materials performance, engineering applications and service experience and failures and reflects the current emphasis with regard to material/environment systems.
Publisher: ASTM International
ISBN: 0803112769
Category : Alloys
Languages : en
Pages : 540
Book Description
Papers included topics of phenomena, basic mechanisms, modeling, test methodologies, materials performance, engineering applications and service experience and failures and reflects the current emphasis with regard to material/environment systems.
Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 486
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 486
Book Description
Structural Integrity of Water Reactor Pressure Boundary Components
Author: Materials Engineering Associates
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 112
Book Description
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 112
Book Description
Proceedings of the U.S. Nuclear Regulatory Commission ... Water Reactor Safety Research Information Meeting
Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 776
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 776
Book Description
Scientific and Technical Aerospace Reports
Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 602
Book Description
Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 602
Book Description
Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.
NRL Report
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 62
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 62
Book Description
Proceedings of the U.S. Nuclear Regulatory Commission Twelfth Water Reactor Safety Research Information Meeting, Held at National Bureau of Standards, Gaithersburg, Maryland, October 22-26, 1983 [i.e. 1984]
Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 400
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 400
Book Description
Sub-critical Crack Growth Along Polymer Interfaces
Author: Charavana Kumara Gurumurthy
Publisher:
ISBN:
Category :
Languages : en
Pages : 500
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 500
Book Description