A Review of Fatigue Crack Growth of Pressure Vessel and Piping Steels in High-temperature, Pressurized Reactor-grade Water

A Review of Fatigue Crack Growth of Pressure Vessel and Piping Steels in High-temperature, Pressurized Reactor-grade Water PDF Author: W. H. Cullen
Publisher:
ISBN:
Category : Fractography
Languages : en
Pages : 134

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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

A Review of Fatigue Crack Growth of Pressure Vessel and Piping Steels in High-temperature, Pressurized Reactor-grade Water PDF Author: W. H. Cullen
Publisher:
ISBN:
Category : Fractography
Languages : en
Pages : 134

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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.

NUREG/CR. PDF Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 518

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Environmentally Assisted Cracking

Environmentally Assisted Cracking PDF Author: W. Barry Lisagor
Publisher: ASTM International
ISBN: 0803112769
Category : Alloys
Languages : en
Pages : 540

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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

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 486

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Structural Integrity of Water Reactor Pressure Boundary Components

Structural Integrity of Water Reactor Pressure Boundary Components PDF Author: Materials Engineering Associates
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 112

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Proceedings of the U.S. Nuclear Regulatory Commission ... Water Reactor Safety Research Information Meeting

Proceedings of the U.S. Nuclear Regulatory Commission ... Water Reactor Safety Research Information Meeting PDF Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 776

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Scientific and Technical Aerospace Reports

Scientific and Technical Aerospace Reports PDF Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 602

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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

NRL Report PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 62

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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]

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] PDF Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 400

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Sub-critical Crack Growth Along Polymer Interfaces

Sub-critical Crack Growth Along Polymer Interfaces PDF Author: Charavana Kumara Gurumurthy
Publisher:
ISBN:
Category :
Languages : en
Pages : 500

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Book Description