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|a (TOE)ost543295
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|a (TOE)543295
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|a E 1.99:doe/er--0313/21
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|a doe/er--0313/21
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|a Extreme embrittlement of austenitic stainless steel irradiated to 75-81 dpa at 335-360{degrees}C
|h [electronic resource]
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|a Oak Ridge, Tenn. :
|b Oak Ridge National Laboratory. ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
|c 1997.
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| 300 |
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|a pp. 197 :
|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 04/01/1997.
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|a "doe/er--0313/21"
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|a "DE97008798"
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|a Porollo, S.I.; Vorobjev, A.N.; Konobeev, Yu.V. [Institute of Physics and Power Engineering, Obninsk (Russian Federation)] [and others]
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|a It is generally accepted that void swelling of austenitic steels ceases below some temperature in the range 340-360°C, and exhibits relatively low swelling rates up to ∼400°C. This perception may not be correct at all irradiation conditions, however, since it was largely developed from data obtained at relatively high displacement rates in fast reactors whose inlet temperatures were in the range 360-370°C. There is an expectation, however, that the swelling regime can shift to lower temperatures at low displacement rates via the well-known {open_quotes}temperature shift{close_quotes} phenomenon. It is also known that the swelling rates at the lower end of the swelling regime increase continuously at a sluggish rate, never approaching the terminal 1%/dpa level within the duration of previous experiments. This paper presents the results of an experiment conducted in the BN-350 fast reactor in Kazakhstan that involved the irradiation of argon-pressurized thin-walled tubes (0-200 MPa hoop stress) constructed from Fe-16Cr-15Ni-3Mo-Nb stabilized steel in contact with the sodium coolant, which enters the reactor at ≈270°C. Tubes in the annealed condition reached 75 dpa at 335°C, and another set in the 20% cold-worked condition reached 81 dpa at 360°C. Upon disassembly all tubes, except those in the stress-free condition, were found to have failed in an extremely brittle fashion. The stress-free tubes exhibited diameter changes that imply swelling levels ranging from 9 to 16%. It is expected that stress-enhancement of swelling induced even larger swelling levels in the stressed tubes.
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|a Austenitic Steels.
|2 local.
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| 650 |
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|a Swelling.
|2 local.
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| 650 |
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|a Physical Radiation Effects.
|2 local.
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| 650 |
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|a Stainless Steels.
|2 local.
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| 650 |
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|a Progress Report.
|2 local.
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| 650 |
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|a Helium Embrittlement.
|2 local.
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| 650 |
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|a Neutrons.
|2 local.
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| 650 |
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|a Temperature Range 0400-1000 K.
|2 local.
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| 650 |
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|a Phase Transformations.
|2 local.
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| 650 |
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|a Materials Science.
|2 edbsc.
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| 710 |
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|a Oak Ridge National Laboratory.
|4 res.
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| 710 |
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|a United States.
|b Department of Energy.
|b Office of Scientific and Technical Information.
|4 dst.
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| 856 |
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|u http://www.osti.gov/scitech/biblio/543295
|z Online Access (via OSTI)
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| 907 |
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|a .b84612745
|b 03-09-23
|c 11-09-15
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| 998 |
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|a web
|b 05-20-19
|c f
|d m
|e p
|f eng
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|a Information bridge
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|s 3f80d24b-ecd0-5151-b6e5-0f50a394ea06
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| 952 |
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|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:doe/er--0313/21
|h Superintendent of Documents classification
|i web
|n 1
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