Stress-corrosion-cracking studies on candidate container alloys for the Tuff Repository

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Description

Cortest Columbus Technologies, Inc. (CC Technologies) investigated the long-term performance of container materials used for high-level waste package as part of the information needed by the Nuclear Regulatory Commission (NRC) to assess the Department of Energy`s application to construct to geologic repository for high-level radioactive waste. At the direction of the NRC, the program focused on the Tuff Repository. This report summarizes the results of Stress-Corrosion-Cracking (SCC) studies performed in Tasks 3, 5, and 7 of the program. Two test techniques were used; U-bend exposures and Slow-Strain-Rate (SSR) tests. The testing was performed on two copper-base alloys (Alloy CDA 102 ... continued below

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Medium: P; Size: 111 p.

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Beavers, J.A. & Durr, C.L. May 1, 1992.

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Description

Cortest Columbus Technologies, Inc. (CC Technologies) investigated the long-term performance of container materials used for high-level waste package as part of the information needed by the Nuclear Regulatory Commission (NRC) to assess the Department of Energy`s application to construct to geologic repository for high-level radioactive waste. At the direction of the NRC, the program focused on the Tuff Repository. This report summarizes the results of Stress-Corrosion-Cracking (SCC) studies performed in Tasks 3, 5, and 7 of the program. Two test techniques were used; U-bend exposures and Slow-Strain-Rate (SSR) tests. The testing was performed on two copper-base alloys (Alloy CDA 102 and Alloy CDA 175) and two Fe-Cr-Ni alloys (Alloy 304L and Alloy 825) in simulated J-13 groundwater and other simulated solutions for the Tuff Repository. These solutions were designed to simulate the effects of concentration and irradiation on the groundwater composition. All SCC testing on the Fe-Cr-Ni Alloys was performed on solution-annealed specimens and thus issues such as the effect of sensitization on SCC were not addressed.

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Medium: P; Size: 111 p.

Notes

INIS; OSTI as TI92015376

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  • Other Information: PBD: May 1992

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  • Other: TI92015376
  • Report No.: NUREG/CR--5710
  • DOI: 10.2172/138436 | External Link
  • Office of Scientific & Technical Information Report Number: 138436
  • Archival Resource Key: ark:/67531/metadc620170

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • May 1, 1992

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • April 22, 2016, 6:17 p.m.

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Beavers, J.A. & Durr, C.L. Stress-corrosion-cracking studies on candidate container alloys for the Tuff Repository, report, May 1, 1992; Washington D.C.. (digital.library.unt.edu/ark:/67531/metadc620170/: accessed December 13, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.