Development and testing ov danadium alloys for fusion applications

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V base alloys have advantages for fusion reactor first-wall and blanket structure. To screen candidate alloys and optimize a V-base alloy, physical and mechanical properties of V-Ti, V-Cr-Ti, and V-Ti- Si alloys were studied before and after irradiation in Li environment in fast fission reactors. V-4Cr-4Ti containing 500-1000 wppM Si and <1000 wppM O+N+C was investigated as the most promising alloy, and more testing is being done. Major results of the work are presented in this paper. The reference V-4Cr-4Ti had the most attractive combination of the mechanical and physical properties that are prerequisite for first-wall and blanket structures: good ... continued below

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26 p.

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Chung, H.M.; Loomis, B.A. & Smith, D.L. October 1, 1996.

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Description

V base alloys have advantages for fusion reactor first-wall and blanket structure. To screen candidate alloys and optimize a V-base alloy, physical and mechanical properties of V-Ti, V-Cr-Ti, and V-Ti- Si alloys were studied before and after irradiation in Li environment in fast fission reactors. V-4Cr-4Ti containing 500-1000 wppM Si and <1000 wppM O+N+C was investigated as the most promising alloy, and more testing is being done. Major results of the work are presented in this paper. The reference V-4Cr-4Ti had the most attractive combination of the mechanical and physical properties that are prerequisite for first-wall and blanket structures: good thermal creep, good tensile strength/ductility, high impact energy, excellent resistance to swelling, and very low ductile-brittle transition temperature before and after irradiation. The alloy was highly resistant to irradiation-induced embrittlement in Li at 420-600 C, and the effects of dynamically charged He on swelling and mechanical properties were insignificant. However, several important issues remain unresolved: welding, low-temperature irradiation, He effect at high dose and high He concentration, irradiation creep, and irradiation performance in air or He. Initial results of investigation of some of these issues are also given.

Physical Description

26 p.

Notes

INIS; OSTI as DE97000681

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  • Fall annual meeting of the Japan Institute of Metals: advanced materials and technology for the 21st century, Honolulu, HI (United States), 13-15 Dec 1995

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  • Other: DE97000681
  • Report No.: ANL/ET/CP--88143
  • Report No.: CONF-951202--4
  • Grant Number: W-31-109-ENG-38
  • Office of Scientific & Technical Information Report Number: 434921
  • Archival Resource Key: ark:/67531/metadc678947

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  • October 1, 1996

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  • July 25, 2015, 2:20 a.m.

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  • Dec. 14, 2015, 6:32 p.m.

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Chung, H.M.; Loomis, B.A. & Smith, D.L. Development and testing ov danadium alloys for fusion applications, article, October 1, 1996; Illinois. (digital.library.unt.edu/ark:/67531/metadc678947/: accessed August 23, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.