Radiation-induced segregation and the relationship to physical properties in irradiated austenitic alloys. [electronic resource]
Radiation-induced changes in composition are studied because these changes can degrade failure of materials irradiated in nuclear reactors. In this work, the effect of alloy composition on radiation-induced segregation, hardening, and void swelling is presented. Five alloys, Fe-18Cr-8Ni, Fe-16Cr-13N...
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| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Washington, D.C. : Oak Ridge, Tenn. :
United States. Department of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
2002.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a Radiation-induced segregation and the relationship to physical properties in irradiated austenitic alloys. |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 2002. | ||
| 300 | |a 12 pages : |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 06/05/2002. | ||
| 500 | |a "anl/nt/cp-107888" | ||
| 500 | |a National Society of Black Physicists Conference, Huntsville, AL (US), 03/13/2002--03/16/2002. | ||
| 500 | |a Allen, T. R.; Cole, J. I.; Was, G. S.; Kenik, E. A. | ||
| 520 | 3 | |a Radiation-induced changes in composition are studied because these changes can degrade failure of materials irradiated in nuclear reactors. In this work, the effect of alloy composition on radiation-induced segregation, hardening, and void swelling is presented. Five alloys, Fe-18Cr-8Ni, Fe-16Cr-13Ni, Fe-18Cr-40Ni, Fe-16Cr-13Ni+Mo, and Fe-16Cr-13Ni+Mo+P (all compositions in wt. %), were irradiated with 3.2 MeV protons at 400 C to a dose of 0.5 displacements per atom. The change in grain boundary composition was measured using field emission gun scanning transmission electron microscopy and the hardening was measured using Vickers indentation. Void swelling is calculated from the void size distribution measured using transmission electron microscopy. After irradiation, Cr depletes and Ni enriches at grain boundaries. Increasing bulk Ni concentration causes greater Cr depletion and Ni enrichment at grain boundaries. For alloys with 16 Cr, the addition of P reduces the Cr depletion and Ni enrichment. Hardening does not directly correlate with composition, but a framework for isolating the effect of hardening and segregation on cracking is suggested. The amount of void swelling in the irradiated material is shown to correspond inversely with segregation. Those alloys with greater segregation tend to swell less. | |
| 536 | |b W-31-109-ENG-38. | ||
| 650 | 7 | |a Alloys. |2 local. | |
| 650 | 7 | |a Distribution. |2 local. | |
| 650 | 7 | |a Field Emission. |2 local. | |
| 650 | 7 | |a Grain Boundaries. |2 local. | |
| 650 | 7 | |a Hardening. |2 local. | |
| 650 | 7 | |a Physical Properties. |2 local. | |
| 650 | 7 | |a Protons. |2 local. | |
| 650 | 7 | |a Reactors. |2 local. | |
| 650 | 7 | |a Segregation. |2 local. | |
| 650 | 7 | |a Swelling. |2 local. | |
| 650 | 7 | |a Irradiation. |2 local. | |
| 650 | 7 | |a Transmission Electron Microscopy. |2 local. | |
| 650 | 7 | |a Physics Of Elementary Particles And Fields. |2 edbsc. | |
| 710 | 2 | |a Argonne 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/797888 |z Online Access (via OSTI) |
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