Fatigue behavior of irradiated helium-containing ferritic steels for fusion reactor applications

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The martensitic alloys 12Cr-1MoVW and 9Cr-1MoVNb have been irradiated in the High Flux Isotope Reactor (HFIR) and subsequently tested in fatigue. In order to achieve helium levels characteristic of fusion reactors, the 12Cr-1MoVW was doped with 1 and 2% Ni, resulting in helium levels of 210 and 410 at. ppM at damage levels of 25 dpa. The 9Cr-1MoVNb was irradiated to a damage level of 3 dpa and contained <5 at. ppM He. Irradiations were carried out at 55/sup 0/C and testing at 22/sup 0/C. No significant changes were found in 9Cr-1MoVNb upon irradiation at this damage level, but effects ... continued below

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Pages: 22

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Grossbeck, M.L.; Vitek, J.M. & Liu, K.C. January 1, 1986.

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Description

The martensitic alloys 12Cr-1MoVW and 9Cr-1MoVNb have been irradiated in the High Flux Isotope Reactor (HFIR) and subsequently tested in fatigue. In order to achieve helium levels characteristic of fusion reactors, the 12Cr-1MoVW was doped with 1 and 2% Ni, resulting in helium levels of 210 and 410 at. ppM at damage levels of 25 dpa. The 9Cr-1MoVNb was irradiated to a damage level of 3 dpa and contained <5 at. ppM He. Irradiations were carried out at 55/sup 0/C and testing at 22/sup 0/C. No significant changes were found in 9Cr-1MoVNb upon irradiation at this damage level, but effects that could possibly be attributed to helium were found in 12Cr-1MoVW. Levels of 210 and 410 at. ppM He produced cyclic strengthening of 29 and 34% over unirradiated nickel-doped materials, respectively. This cyclic hardening attributable largely to helium resulted in degradation of the cyclic life. However, the fatigue life remained comparable to or better than unirradiated 20%-cold-worked 316 stainless steel.

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Pages: 22

Notes

NTIS, PC A02/MF A01.

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  • 2. international conference on fusion reactor materials (ICFRM-2), Chicago, IL, USA, 13 Apr 1986

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  • Other: DE86011973
  • Report No.: CONF-860421-53
  • Grant Number: AC05-84OR21400
  • Office of Scientific & Technical Information Report Number: 5756371
  • Archival Resource Key: ark:/67531/metadc1099951

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  • January 1, 1986

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  • Feb. 18, 2018, 3:59 p.m.

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  • May 11, 2018, 2:38 p.m.

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Grossbeck, M.L.; Vitek, J.M. & Liu, K.C. Fatigue behavior of irradiated helium-containing ferritic steels for fusion reactor applications, article, January 1, 1986; Tennessee. (digital.library.unt.edu/ark:/67531/metadc1099951/: accessed October 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.