Integrity of PWR pressure vessels during overcooling accidents

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The reactor pressure vessel in a pressurized water reactor is normally subjected to temperatures and pressures that preclude propagation of sharp, crack-like defects that might exist in the wall of the vessel. However, there is a class of postulated accidents, referred to as overcooling accidents, that can subject the pressure vessel to severe thermal shock while the pressure is substantial. As a result of such accidents vessels containing high concentrations of copper and nickel, which enhance radiation embrittlement, may possess a potential for extensive propagation of preexistent inner surface flaws prior to the vessel's normal end of life. For the ... continued below

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Pages: 27

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Cheverton, R.D.; Iskander, S.K. & Whitman, G.D. January 1, 1982.

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Description

The reactor pressure vessel in a pressurized water reactor is normally subjected to temperatures and pressures that preclude propagation of sharp, crack-like defects that might exist in the wall of the vessel. However, there is a class of postulated accidents, referred to as overcooling accidents, that can subject the pressure vessel to severe thermal shock while the pressure is substantial. As a result of such accidents vessels containing high concentrations of copper and nickel, which enhance radiation embrittlement, may possess a potential for extensive propagation of preexistent inner surface flaws prior to the vessel's normal end of life. For the purpose of evaluating this problem a state-of-the-art fracture mechanics model was developed and has been used for conducting parametric analyses and for calculating several recorded PWR transients. Results of the latter analysis indicate that there may be some vessels that have a potential for failure today if subjected to a Rancho Seco (1978) or TMI-2 (1979) type transient. However, the calculational model may be excessively conservative, and this possibility is under investigation.

Physical Description

Pages: 27

Notes

NTIS, PC A03/MF A01.

Source

  • International meeting on thermal nuclear reactor safety, Chicago, IL, USA, 29 Aug 1982

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  • Other: DE82020812
  • Report No.: CONF-820802-12
  • Grant Number: W-7405-ENG-26
  • Office of Scientific & Technical Information Report Number: 5091593
  • Archival Resource Key: ark:/67531/metadc1056549

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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, 1982

Added to The UNT Digital Library

  • Jan. 22, 2018, 7:23 a.m.

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  • Feb. 1, 2018, 1:31 p.m.

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Cheverton, R.D.; Iskander, S.K. & Whitman, G.D. Integrity of PWR pressure vessels during overcooling accidents, article, January 1, 1982; Tennessee. (digital.library.unt.edu/ark:/67531/metadc1056549/: accessed April 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.