Effect of Light-Water Reactor Environments on Fatigue Crack Growth Rate in Reactor Pressure Vessel Steels PDF Download
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Author: WH. Cullen
Publisher:
ISBN:
Category : Aluminum alloys
Languages : en
Pages : 22
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Book Description
This paper presents an overview of the effect of light-water reactor environments on the fatigue crack growth rate in reactor pressure vessel steels. The effect of different variables known to influence the environmental assistance--stress intensity range, load ratio, frequency, temperature, water chemistry, and irradiation--is described. The fractographic phenomena and mechanisms of fatigue crack propagation associated with environmental influence is emphasized. An analytical approach for predicting the crack growth rates based on the hydrogen embrittlement model is described. Finally, a discussion of the effect of different transients occurring in the nuclear reactors on the crack growth rate predictions is presented.
Author: WH. Cullen
Publisher:
ISBN:
Category : Aluminum alloys
Languages : en
Pages : 22
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Book Description
This paper presents an overview of the effect of light-water reactor environments on the fatigue crack growth rate in reactor pressure vessel steels. The effect of different variables known to influence the environmental assistance--stress intensity range, load ratio, frequency, temperature, water chemistry, and irradiation--is described. The fractographic phenomena and mechanisms of fatigue crack propagation associated with environmental influence is emphasized. An analytical approach for predicting the crack growth rates based on the hydrogen embrittlement model is described. Finally, a discussion of the effect of different transients occurring in the nuclear reactors on the crack growth rate predictions is presented.
Author: W. H. Cullen
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 80
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Book Description
Author: RH. Emanuelson
Publisher:
ISBN:
Category : Aqueous environments
Languages : en
Pages : 19
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Book Description
This paper presents the results of experiments to determine which variables have the most effect on environmentally assisted cracking (EAC) of reactor pressure vessel steels. Four heats of SA508 and three heats of SA533 were studied in 288°C pressurized water reactor, light water reactor, and boiling water reactor environments. The sulfur content of these materials ranged from 0.004 to 0.025%. The most important variable was found to be the sulfur content and sulfur morphology of the material. A material with a bulk sulfur content greater than 0.010% may be susceptible to EAC. The loading frequency was found to be an important variable. Minor effects of EAC were attributed to the load ratio, ?K level, and oxygen content of the environment. An experimental method to introduce sulfur directly to the crack tip is described. A time-based method of data interpretation is discussed.
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).
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
Results are presented from an experimental program being conducted to investigate the effects of pressurized water reactor environment on the fatigue crack growth rate of pressure vessel steels. Tests were conducted on precracked WOL type specimens under load controlled conditions. The effects of R ratio, loading rates, and loading wave form are evaluated, and the results are compared for both forging and plate material, as well as weldments.
Author: William Alan Van der Sluys
Publisher: ASTM International
ISBN: 0803124082
Category : Metals
Languages : en
Pages : 304
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Book Description
Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 776
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Book Description
Author: Materials Engineering Associates
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 120
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Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
Section 111 of the ASME Boiler and Pressure Vessel Code specifies fatigue design curves for structural materials. The effects of reactor coolant environments are not explicitly addressed by the Code design curves. Recent test data illustrate potentially significant effects of light water reactor (LWR) coolant environments on the fatigue resistance of carbon and low-alloy steels. Under certain loading and environmental conditions, fatigue lives of test specimens may be shorter than those in air by a factor of[approx]70. The crack initiation and crack growth characteristics of carbon and low-alloy steels in LWR environments are presented. Decreases in fatigue life of these steels in high-dissolved-oxygen water are caused primarily by the effect of environment on growth of short cracks
Author: R. Rungta
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 128
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Book Description
