MARC

LEADER 00000nam a22000003u 4500
001 b9053512
003 CoU
005 20160923222808.5
006 m o d f
007 cr |||||||||||
008 170215e19800301||| ot f0|||||eng|d
035 |a (TOE)ost5493697 
035 |a (TOE)5493697 
040 |a TOE  |c TOE 
049 |a GDWR 
072 7 |a 36  |2 edbsc 
072 7 |a 21  |2 edbsc 
086 0 |a E 1.99:ornl/tm-7134 
086 0 |a E 1.99:ornl/tm-7134 
088 |a ornl/tm-7134 
245 0 0 |a Analysis of available creep and creep-rupture data for commercially heat-treated alloy 718  |h [electronic resource] 
260 |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. 
300 |a Pages: (63 p) :  |b digital, PDF file. 
336 |a text  |b txt  |2 rdacontent. 
337 |a computer  |b c  |2 rdamedia. 
338 |a online resource  |b cr  |2 rdacarrier. 
500 |a Published through SciTech Connect. 
500 |a 03/01/1980. 
500 |a "ornl/tm-7134" 
500 |a "DE91015628" 
500 |a Booker, M.K.; Booker, B.L.P. 
520 3 |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. 
536 |b AC05-84OR21400. 
650 7 |a Inconel 718.  |2 local. 
650 7 |a Creep.  |2 local. 
650 7 |a Aging.  |2 local. 
650 7 |a Chemical Composition.  |2 local. 
650 7 |a Heat Treatments.  |2 local. 
650 7 |a Lmfbr Type Reactors.  |2 local. 
650 7 |a Reactor Materials.  |2 local. 
650 7 |a Ruptures.  |2 local. 
650 7 |a Alloy-Ni53cr19fe19nb5mo3.  |2 local. 
650 7 |a Alloys.  |2 local. 
650 7 |a Aluminium Additions.  |2 local. 
650 7 |a Aluminium Alloys.  |2 local. 
650 7 |a Breeder Reactors.  |2 local. 
650 7 |a Chromium Alloys.  |2 local. 
650 7 |a Corrosion Resistant Alloys.  |2 local. 
650 7 |a Epithermal Reactors.  |2 local. 
650 7 |a Failures.  |2 local. 
650 7 |a Fast Reactors.  |2 local. 
650 7 |a Fbr Type Reactors.  |2 local. 
650 7 |a Heat Resistant Materials.  |2 local. 
650 7 |a Heat Resisting Alloys.  |2 local. 
650 7 |a Inconel Alloys.  |2 local. 
650 7 |a Iron Alloys.  |2 local. 
650 7 |a Liquid Metal Cooled Reactors.  |2 local. 
650 7 |a Materials.  |2 local. 
650 7 |a Mechanical Properties.  |2 local. 
650 7 |a Molybdenum Alloys.  |2 local. 
650 7 |a Nickel Alloys.  |2 local. 
650 7 |a Nickel Base Alloys.  |2 local. 
650 7 |a Niobium A.  |2 local. 
650 7 |a Reactors.  |2 local. 
650 7 |a Materials Science.  |2 edbsc. 
650 7 |a Specific Nuclear Reactors And Associated Plants.  |2 edbsc. 
710 2 |a Oak Ridge National Laboratory.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |4 spn. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
856 4 0 |u http://www.osti.gov/scitech/biblio/5493697  |z Online Access (via OSTI) 
907 |a .b90535121  |b 03-09-23  |c 02-15-17 
998 |a web  |b 02-15-17  |c f  |d m   |e p  |f eng  |g    |h 0  |i 1 
956 |a Information bridge 
999 f f |i 7d92d179-036e-5a61-9a99-3365b6f145eb  |s 1c2d0344-f948-5005-b0b8-625f59ee84a5 
952 f f |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