Steam generator tube integrity program. Phase I report. [PWR]

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The results are presented of the pressure tests performed as part of Phase I of the Steam Generator Tube Integrity (SGTI) program at Battelle Pacific Northwest Laboratory. These tests were performed to establish margin-to-failure predictions for mechanically defected Pressurized Water Reactor (PWR) steam generator tubing under operating and accident conditions. Defect geometries tested were selected because they simulate known or expected defects in PWR steam generators. These defect geometries are Electric Discharge Machining (EDM) slots, elliptical wastage, elliptical wastage plus through-wall slot, uniform thinning, denting, denting plus uniform thinning, and denting plus elliptical wastage. All defects were placed in tubing ... continued below

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Alzheimer, J.M.; Clark, R.A.; Morris, C.J. & Vagins, M. September 1, 1979.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 27 times . More information about this report can be viewed below.

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  • Pacific Northwest Laboratory
    Publisher Info: Battelle Pacific Northwest Labs., Richland, WA (USA)
    Place of Publication: Richland, Washington

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Description

The results are presented of the pressure tests performed as part of Phase I of the Steam Generator Tube Integrity (SGTI) program at Battelle Pacific Northwest Laboratory. These tests were performed to establish margin-to-failure predictions for mechanically defected Pressurized Water Reactor (PWR) steam generator tubing under operating and accident conditions. Defect geometries tested were selected because they simulate known or expected defects in PWR steam generators. These defect geometries are Electric Discharge Machining (EDM) slots, elliptical wastage, elliptical wastage plus through-wall slot, uniform thinning, denting, denting plus uniform thinning, and denting plus elliptical wastage. All defects were placed in tubing representative of that currently used in PWR steam generators.

Notes

Dep. NTIS, PC A12/MF A01.

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  • Report No.: NUREG/CR-0718
  • Report No.: PNL-2937
  • Grant Number: EY-76-C-06-1830
  • DOI: 10.2172/5920767 | External Link
  • Office of Scientific & Technical Information Report Number: 5920767
  • Archival Resource Key: ark:/67531/metadc1099598

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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

  • September 1, 1979

Added to The UNT Digital Library

  • Feb. 18, 2018, 3:59 p.m.

Description Last Updated

  • April 19, 2018, 7:31 p.m.

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Alzheimer, J.M.; Clark, R.A.; Morris, C.J. & Vagins, M. Steam generator tube integrity program. Phase I report. [PWR], report, September 1, 1979; Richland, Washington. (https://digital.library.unt.edu/ark:/67531/metadc1099598/: accessed May 23, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.