Long-term creep and creep-rupture behavior of Types 304 and 316 stainless steel, Type 316 casting material (CF8M), and 2 1/4 Cr-1 Mo steel. Final report [electronic resource]
Final results of long-term creep and creep-rupture tests are compiled and summarized for a number of structural materials evaluated in support of the Liquid Metal Reactor program. These materials include type 304 stainless steel (tested to 13.4 years), type 316 stainless steel (tested to 8.2 years),...
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Online Access (via OSTI) |
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| Corporate Author: | |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Oak Ridge, Tenn. : Oak Ridge, Tenn. :
Oak Ridge National Laboratory. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
1986.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a Long-term creep and creep-rupture behavior of Types 304 and 316 stainless steel, Type 316 casting material (CF8M), and 2 1/4 Cr-1 Mo steel. Final report |h [electronic resource] |
| 260 | |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 1986. | ||
| 300 | |a 152 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 06/01/1986. | ||
| 500 | |a "ornl/tm--9896" | ||
| 500 | |a "TI86026923" | ||
| 500 | |a Brinkman, C R; Booker, M K; Sikka, V K; McCoy, H E. | ||
| 520 | 3 | |a Final results of long-term creep and creep-rupture tests are compiled and summarized for a number of structural materials evaluated in support of the Liquid Metal Reactor program. These materials include type 304 stainless steel (tested to 13.4 years), type 316 stainless steel (tested to 8.2 years), CF8M or type 316 stainless casting (tested to 2.5 years), and 2 1/4 Cr-1 Mo steel (tested to 6.5 years). Creep curves of all materials evaluated, representative metallography, and hardness data taken subsequent to testing are also included. Comparisons are made between predictions made several years ago with preliminary creep and creep-rupture data and final results obtained under this program. | |
| 536 | |b AC05-84OR21400. | ||
| 650 | 7 | |a Stainless Steel-304. |2 local. | |
| 650 | 7 | |a Creep. |2 local. | |
| 650 | 7 | |a Materials Testing. |2 local. | |
| 650 | 7 | |a Reactor Materials. |2 local. | |
| 650 | 7 | |a Stainless Steel-316. |2 local. | |
| 650 | 7 | |a Chromium-Molybdenum Steels. |2 local. | |
| 650 | 7 | |a Lmfbr Type Reactors. |2 local. | |
| 650 | 7 | |a Ruptures. |2 local. | |
| 650 | 7 | |a Microstructure. |2 local. | |
| 650 | 7 | |a Ductility. |2 local. | |
| 650 | 7 | |a Aging. |2 local. | |
| 650 | 7 | |a Specific Nuclear Reactors And Associated Plants. |2 edbsc. | |
| 650 | 7 | |a Materials Science. |2 edbsc. | |
| 710 | 2 | |a Oak Ridge National Laboratory. |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/scitech/biblio/712353 |z Online Access (via OSTI) |
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