Steam generator tube integrity program leak rate tests. Progress report

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Description

This interim report presents preliminary results on leak rate tests performed on through-wall defected Inconel 600 steam generator tubing. Tube defects included an EDM (electro-discharge machine) notch and IGSCC (intergranular stress corrosion cracks) of various lengths. Tests were conducted at PWR operating temperatures with leakage of hot water/steam into air. A number of IGSCC cracks were unstable under the experiment conditions of these initial tests, continuing to grow until system capacity limitations resulted in decreased pressure differential. However, initial tesing also pointed to a need for reconfiguration of the test apparatus to sustain increased flow and, more importantly, alter the ... continued below

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Clark, R.A. & Bickford, R.L. January 1, 1984.

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Description

This interim report presents preliminary results on leak rate tests performed on through-wall defected Inconel 600 steam generator tubing. Tube defects included an EDM (electro-discharge machine) notch and IGSCC (intergranular stress corrosion cracks) of various lengths. Tests were conducted at PWR operating temperatures with leakage of hot water/steam into air. A number of IGSCC cracks were unstable under the experiment conditions of these initial tests, continuing to grow until system capacity limitations resulted in decreased pressure differential. However, initial tesing also pointed to a need for reconfiguration of the test apparatus to sustain increased flow and, more importantly, alter the mode of control. The initial test configuration is based on flow control, with pressure differential across the specimen an independent variable. This often results in pressure increases too rapid to establish the initiation of crack instability. A reconfigured system based on pressure control with flow as an independent parameter is being recommended for future tests.

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NTIS, PC A04/MF A01; 1 - GPO

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  • Other Information: Portions are illegible in microfiche products

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  • Other: DE84006054
  • Report No.: NUREG/CR-3562
  • Report No.: PNL-4629
  • Grant Number: AC06-76RL01830
  • DOI: 10.2172/5388200 | External Link
  • Office of Scientific & Technical Information Report Number: 5388200
  • Archival Resource Key: ark:/67531/metadc1064066

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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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Creation Date

  • January 1, 1984

Added to The UNT Digital Library

  • Feb. 4, 2018, 10:51 a.m.

Description Last Updated

  • April 20, 2018, 6:04 p.m.

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Clark, R.A. & Bickford, R.L. Steam generator tube integrity program leak rate tests. Progress report, report, January 1, 1984; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc1064066/: accessed May 25, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.