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|a (TOE)ost5493697
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|a (TOE)5493697
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|a E 1.99:ornl/tm-7134
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|a E 1.99:ornl/tm-7134
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|a ornl/tm-7134
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|a Analysis of available creep and creep-rupture data for commercially heat-treated alloy 718
|h [electronic resource]
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|a Washington, D.C. :
|b United States. Department of Energy ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
|c 1980.
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|a Pages: (63 p) :
|b digital, PDF file.
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|a text
|b txt
|2 rdacontent.
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|a computer
|b c
|2 rdamedia.
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|a online resource
|b cr
|2 rdacarrier.
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|a Published through SciTech Connect.
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|a 03/01/1980.
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|a "ornl/tm-7134"
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|a "DE91015628"
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|a Booker, M.K.; Booker, B.L.P.
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|a The Ni-Cr-Fe-Nb alloy 718 is a widely used material in elevated- temperature applications. Currently, it is approved by the American Society of Mechanical Engineers ASME Boiler and Pressure Vessel Code only as a bolting material for elevated-temperature nuclear service. This report presents analyses of available creep and creep-rupture data for commercially heat-treated alloy 718 toward the development of allowable stress levels for this material in general elevated-temperature nuclear service. Available data came from 14 heats of bar, plate, and forging material over the temperature range from 538 to 704°C. The longest rupture time encompassed by the data was almost 87,000 h. Generalized regression analyses were performed to yield an analytical expression for rupture life as a function of stress and temperature. Heat-to-heat variations were accounted for by lot-centering'' the data. Effects of different solution heat treatment temperatures (T{sub s}) were accounted for by normalizing the creep stresses to the data for T{sub s} = 954°C. Thus, the results are strictly applicable only for material with this solution treatment. Time and strain to tertiary creep were predicted as functions of rupture life. Creep strain-time data were represented by normalization to the time and strain to tertiary creep and development of master creep curves.'' The results allow estimation of time-dependent allowable stress per American Society of Mechanical Engineers Code Class N-47, and the creep strain-time relationships can be used to develop isochronous stress-strain curves. 29 refs., 44 figs., 14 tabs.
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|b AC05-84OR21400.
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|a Inconel 718.
|2 local.
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|a Creep.
|2 local.
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|a Aging.
|2 local.
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|a Chemical Composition.
|2 local.
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|a Heat Treatments.
|2 local.
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|a Lmfbr Type Reactors.
|2 local.
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|a Reactor Materials.
|2 local.
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|a Ruptures.
|2 local.
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|a Alloy-Ni53cr19fe19nb5mo3.
|2 local.
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|a Alloys.
|2 local.
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|a Aluminium Additions.
|2 local.
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7 |
|a Aluminium Alloys.
|2 local.
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7 |
|a Breeder Reactors.
|2 local.
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7 |
|a Chromium Alloys.
|2 local.
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|
7 |
|a Corrosion Resistant Alloys.
|2 local.
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|a Epithermal Reactors.
|2 local.
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|a Failures.
|2 local.
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|a Fast Reactors.
|2 local.
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|
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|a Fbr Type Reactors.
|2 local.
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|a Heat Resistant Materials.
|2 local.
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|a Heat Resisting Alloys.
|2 local.
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|a Inconel Alloys.
|2 local.
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7 |
|a Iron Alloys.
|2 local.
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650 |
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|a Liquid Metal Cooled Reactors.
|2 local.
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650 |
|
7 |
|a Materials.
|2 local.
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|a Mechanical Properties.
|2 local.
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|a Molybdenum Alloys.
|2 local.
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|a Nickel Alloys.
|2 local.
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|a Nickel Base Alloys.
|2 local.
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|a Niobium A.
|2 local.
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|a Reactors.
|2 local.
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|
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|a Materials Science.
|2 edbsc.
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|a Specific Nuclear Reactors And Associated Plants.
|2 edbsc.
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2 |
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|a Oak Ridge National Laboratory.
|4 res.
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1 |
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|a United States.
|b Department of Energy.
|4 spn.
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1 |
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|a United States.
|b Department of Energy.
|b Office of Scientific and Technical Information.
|4 dst.
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4 |
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|u http://www.osti.gov/scitech/biblio/5493697
|z Online Access (via OSTI)
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907 |
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|a .b90535121
|b 03-09-23
|c 02-15-17
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|a web
|b 02-15-17
|c f
|d m
|e p
|f eng
|g
|h 0
|i 1
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|a Information bridge
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|i 7d92d179-036e-5a61-9a99-3365b6f145eb
|s 1c2d0344-f948-5005-b0b8-625f59ee84a5
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|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:ornl/tm-7134
|h Superintendent of Documents classification
|i web
|n 1
|