MARC

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035 |a (TOE)ost5194753 
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086 0 |a E 1.99:hedl-tme-72-95 
086 0 |a E 1.99:hedl-tme-72-95 
088 |a hedl-tme-72-95 
245 0 0 |a Length changes in FTR prototypic cladding irradiated in EBR-II to 1 x 10²² N/CM², E > 0. 1 MeV (PIN B-65)(RM-24)  |h [electronic resource] 
260 |a Richland, Wash. :  |b Hanford Site (Wash.) ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,  |c 1972. 
300 |a Pages: 50 :  |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 the Information Bridge: DOE Scientific and Technical Information. 
500 |a 07/01/1972. 
500 |a "hedl-tme-72-95" 
500 |a Straalsund, J.L.; Guthrie, G.L.; Larson, T.J. 
520 3 |a Swelling in prototypic FTR cladding and duct specimens is being determined from a series of three irradiations designed to cover a range of temperatures approximately 800 to 1500°F and peak fluences of approximately 1 x 10²², 6 x 10²², and 1 x 10²³ n/cm². The length change measurements for the low fluence irradiation have been completed and are summarized in this report. No swelling, only shrinkage, was found in the 20 percent cold worked Type 316 stainless steel cladding specimens. This shrinkage is of the same magnitude and has the same temperature dependency as unirradiated, control samples. Annealed specimens did swell slightly. Details of the experiment and analysis are given. 
536 |b EY-76-C-14-2170. 
650 7 |a Test Reactors.  |2 local. 
650 7 |a Liquid Metal Cooled Reactors.  |2 local. 
650 7 |a Nickel Alloys.  |2 local. 
650 7 |a Research And Test Reactors.  |2 local. 
650 7 |a Radiation Effects.  |2 local. 
650 7 |a Sodium Cooled Reactors.  |2 local. 
650 7 |a Chromium Steels.  |2 local. 
650 7 |a Alloys.  |2 local. 
650 7 |a Steels.  |2 local. 
650 7 |a Length.  |2 local. 
650 7 |a Iron Base Alloys.  |2 local. 
650 7 |a Heat Resisting Alloys.  |2 local. 
650 7 |a Dimensions.  |2 local. 
650 7 |a Epithermal Reactors.  |2 local. 
650 7 |a Reactors.  |2 local. 
650 7 |a Stainless Steels.  |2 local. 
650 7 |a Stainless Steel-316.  |2 local. 
650 7 |a Fftf Reactor.  |2 local. 
650 7 |a Chromium-nickel Steels.  |2 local. 
650 7 |a Molybdenum Alloys.  |2 local. 
650 7 |a Chromium Alloys.  |2 local. 
650 7 |a Fast Reactors.  |2 local. 
650 7 |a Fuel Cans.  |2 local. 
650 7 |a Physical Radiation Effects.  |2 local. 
650 7 |a Shrinkage.  |2 local. 
650 7 |a Corrosion Resistant Alloys.  |2 local. 
650 7 |a Iron Alloys.  |2 local. 
650 7 |a Research Reactors.  |2 local. 
650 7 |a Specific Nuclear Reactors And Associated Plants.  |2 edbsc. 
710 2 |a Hanford Engineering Development Laboratory.  |4 res. 
710 2 |a Hanford Site (Wash.).  |4 res. 
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/servlets/purl/5194753-vvkyhU/  |z Online Access 
907 |a .b72869537  |b 03-07-23  |c 02-08-13 
998 |a web  |b 02-08-13  |c f  |d m   |e p  |f eng  |g wau  |h 0  |i 1 
956 |a Information bridge 
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952 f f |p Can circulate  |a University of Colorado Boulder  |b Online  |c Online  |d Online  |e E 1.99:hedl-tme-72-95  |h Superintendent of Documents classification  |i web  |n 1