Irradiation-assisted stress corrosion cracking of HTH Alloy X-750 and Alloy 625

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In-reactor testing of bolt-loaded compact tension specimens was performed in 360 C water. New data confirms previous results that high irradiation levels reduce SCC resistance in Alloy X-750. Low boron heats show improved IASCC (irradiation-assisted stress corrosion cracking). Alloy 625 is resistant to IASCC. Microstructural, microchemical, and deformation studies were carried out. Irradiation of X-750 caused significant strengthening and ductility loss associated with formation of cavities and dislocation loops. High irradiation did not cause segregation in X-750. Irradiation of 625 resulted in formation of small dislocation loops and a fine body-centered-orthorhombic phase. The strengthening due to loops and precipitates was ... continued below

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14 p.

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Bajaj, R.; Mills, W.J.; Lebo, M.R.; Hyatt, B.Z. & Burke, M.G. July 1, 1995.

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Description

In-reactor testing of bolt-loaded compact tension specimens was performed in 360 C water. New data confirms previous results that high irradiation levels reduce SCC resistance in Alloy X-750. Low boron heats show improved IASCC (irradiation-assisted stress corrosion cracking). Alloy 625 is resistant to IASCC. Microstructural, microchemical, and deformation studies were carried out. Irradiation of X-750 caused significant strengthening and ductility loss associated with formation of cavities and dislocation loops. High irradiation did not cause segregation in X-750. Irradiation of 625 resulted in formation of small dislocation loops and a fine body-centered-orthorhombic phase. The strengthening due to loops and precipitates was apparently offset in 625 by partial dissolution of {gamma} precipitates. Transmutation of boron to helium at grain boundaries, coupled with matrix strengthening, is believed to be responsible for IASCC in X-750, and the absence of these two effects results in superior IASCC resistance in 625.

Physical Description

14 p.

Notes

INIS; OSTI as DE95014553

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  • 7. international symposium on environmental degradation of materials in nuclear power plants: water reactors, Breckenridge, CO (United States), 6-10 Aug 1995

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  • Other: DE95014553
  • Report No.: WAPD-T--3054
  • Report No.: CONF-950816--1
  • Grant Number: AC11-93PN38195
  • Office of Scientific & Technical Information Report Number: 81972
  • Archival Resource Key: ark:/67531/metadc739330

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Office of Scientific & Technical Information Technical Reports

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  • July 1, 1995

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  • Oct. 18, 2015, 6:40 p.m.

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  • Dec. 7, 2015, 5:58 p.m.

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Bajaj, R.; Mills, W.J.; Lebo, M.R.; Hyatt, B.Z. & Burke, M.G. Irradiation-assisted stress corrosion cracking of HTH Alloy X-750 and Alloy 625, article, July 1, 1995; United States. (digital.library.unt.edu/ark:/67531/metadc739330/: accessed September 22, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.