Fracture-mechanics data deduced from thermal-shock and related experiments with LWR pressure-vessel material

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Pressurized water reactors (PWRs) are susceptible to certain types of hypothetical accidents that can subject the reactor pressure vessel to severe thermal shock, that is, a rapid cooling of the inner surface of the vessel wall. The thermal-shock loading, coupled with the radiation-induced reduction in the material fracture toughness, introduces the possibility of propagation of preexistent flaws and what at one time were regarded as somewhat unique fracture-oriented conditions. Several postulated reactor accidents have been analyzed to discover flaw behavior trends; seven intermediate-scale thermal-shock experiments with steel cylinders have been conducted; and corresponding materials characterization studies have been performed. Flaw ... continued below

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Pages: 38

Creation Information

Cheverton, R.D.; Canonico, D.A.; Iskander, S.K.; Bolt, S.E.; Holz, P.P.; Nanstad, R.K. et al. January 1, 1982.

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Description

Pressurized water reactors (PWRs) are susceptible to certain types of hypothetical accidents that can subject the reactor pressure vessel to severe thermal shock, that is, a rapid cooling of the inner surface of the vessel wall. The thermal-shock loading, coupled with the radiation-induced reduction in the material fracture toughness, introduces the possibility of propagation of preexistent flaws and what at one time were regarded as somewhat unique fracture-oriented conditions. Several postulated reactor accidents have been analyzed to discover flaw behavior trends; seven intermediate-scale thermal-shock experiments with steel cylinders have been conducted; and corresponding materials characterization studies have been performed. Flaw behavior trends and related fracture-mechanics data deduced from these studies are discussed.

Physical Description

Pages: 38

Notes

NTIS, PC A03/MF A01.

Source

  • ASME pressure vessel and piping conference, Orlando, FL, USA, 27 Jun 1982

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  • Other: DE82018162
  • Report No.: CONF-820601-22
  • Grant Number: W-7405-ENG-26
  • Office of Scientific & Technical Information Report Number: 5163254
  • Archival Resource Key: ark:/67531/metadc1056161

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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, 1982

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  • Jan. 22, 2018, 7:23 a.m.

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  • Feb. 1, 2018, 6:26 p.m.

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Cheverton, R.D.; Canonico, D.A.; Iskander, S.K.; Bolt, S.E.; Holz, P.P.; Nanstad, R.K. et al. Fracture-mechanics data deduced from thermal-shock and related experiments with LWR pressure-vessel material, article, January 1, 1982; Tennessee. (digital.library.unt.edu/ark:/67531/metadc1056161/: accessed April 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.