Environmental factors influencing stress corrosion cracking in boiling water reactors

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The mechanisms of intergranular stress corrosion cracking (IGSCC) of sensitized stainless steels in boiling water reactor (BWR) primary coolant are reviewed, with emphasis on the role the environment plays on both the initiation and propagation processes. Environmental factors discussed include oxygen (corrosion potential), temperature, and dissolved ions in the water and the range of strain rates at which IGSCC occurs. Both crack propagation rates and the range of strain rates at which IGSCC occurs decrease rapidly as temperature is increased above approximately 200/sup 0/C, in essentially the same manner as the solubility of magnetite decreases in acidic solutions. A mechanism ... continued below

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Pages: 26

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Weeks, J.R. January 1, 1984.

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Description

The mechanisms of intergranular stress corrosion cracking (IGSCC) of sensitized stainless steels in boiling water reactor (BWR) primary coolant are reviewed, with emphasis on the role the environment plays on both the initiation and propagation processes. Environmental factors discussed include oxygen (corrosion potential), temperature, and dissolved ions in the water and the range of strain rates at which IGSCC occurs. Both crack propagation rates and the range of strain rates at which IGSCC occurs decrease rapidly as temperature is increased above approximately 200/sup 0/C, in essentially the same manner as the solubility of magnetite decreases in acidic solutions. A mechanism of crack propagation is presented base on this observation. To establish water chemistry guidelines for crack-free operation of BWR's containing sensitized stainless steel, more information is needed on the role of absorption of impurities in the surface and deposited oxides and on the interaction between the oxygen and impurity levels required to maintain an electrochemical potential in a range where IGSCC is unlikely to occur. The relative effects of short bursts of impurities and longer term lower concentrations of these same impurities also need to be evaluated.

Physical Description

Pages: 26

Notes

NTIS, PC A03/MF A01 - GPO.

Source

  • EFC-ACHEMA meeting on environment sensitive cracking problems in nuclear installations containing high temperature water, Munich, F.R. Germany, 17 Sep 1984

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  • Other: TI85003205
  • Report No.: BNL-NUREG-35428
  • Report No.: CONF-8409188-1
  • Grant Number: AC02-76CH00016
  • Office of Scientific & Technical Information Report Number: 6164492
  • Archival Resource Key: ark:/67531/metadc1112714

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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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  • January 1, 1984

Added to The UNT Digital Library

  • Feb. 22, 2018, 7:45 p.m.

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  • April 23, 2018, 4:03 p.m.

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Weeks, J.R. Environmental factors influencing stress corrosion cracking in boiling water reactors, article, January 1, 1984; Upton, New York. (digital.library.unt.edu/ark:/67531/metadc1112714/: accessed November 18, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.