Reactor pressure vessel structural integrity research in the US Nuclear Regulatory Commission HSST and HSSI Programs

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This report discusses development on the technology used to assess the safety of irradiation-embrittled nuclear reactor pressure vessels containing flaws. Fracture mechanics tests on reactor pressure vessel steel have shown that local brittle zones do not significantly degrade the material fracture toughness, constraint relaxation at the crack tip of shallow surface flaws results in increased fracture toughness, and biaxial loading reduces but does not eliminate the shallow-flaw fracture toughness elevation. Experimental irradiation investigations have shown that the irradiation-induced shift in Charpy V-notch versus temperature behavior may not be adequate to conservatively assess fracture toughness shifts due to embrittlement and the ... continued below

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10 p.

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Pennell, W.E. & Corwin, W.R. February 1, 1994.

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Description

This report discusses development on the technology used to assess the safety of irradiation-embrittled nuclear reactor pressure vessels containing flaws. Fracture mechanics tests on reactor pressure vessel steel have shown that local brittle zones do not significantly degrade the material fracture toughness, constraint relaxation at the crack tip of shallow surface flaws results in increased fracture toughness, and biaxial loading reduces but does not eliminate the shallow-flaw fracture toughness elevation. Experimental irradiation investigations have shown that the irradiation-induced shift in Charpy V-notch versus temperature behavior may not be adequate to conservatively assess fracture toughness shifts due to embrittlement and the wide global variations of initial chemistry and fracture properties of a nominally uniform material within a pressure vessel may confound accurate integrity assessments that require baseline properties.

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10 p.

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INIS; OSTI as DE94006550

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  • British Nuclear Energy Society international conference on thermal reactor safety assessment, Manchester (United Kingdom), 23-26 May 1994

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  • Other: DE94006550
  • Report No.: CONF-940594--1
  • Grant Number: AC05-84OR21400
  • Office of Scientific & Technical Information Report Number: 142554
  • Archival Resource Key: ark:/67531/metadc626734

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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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  • February 1, 1994

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  • June 16, 2015, 7:43 a.m.

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  • April 7, 2016, 8:32 p.m.

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Pennell, W.E. & Corwin, W.R. Reactor pressure vessel structural integrity research in the US Nuclear Regulatory Commission HSST and HSSI Programs, article, February 1, 1994; Tennessee. (digital.library.unt.edu/ark:/67531/metadc626734/: accessed November 17, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.