The inclusion of weld residual stress in fracture margin assessments of embrittled nuclear reactor pressure vessels

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Description

Analyses were performed to determine the impact of weld residual stresses in a reactor pressure vessel (RPV) on (1) the generation of pressure temperature (P-T) curves required for maintaining specified fracture prevention margins during nuclear plant startup and shutdown, and (2) the conditional probability of vessel failure due to pressurized thermal shock (PTS) loading. The through wall residual stress distribution in an axially oriented weld was derived using measurements taken from a shell segment of a canceled RPV and finite element thermal stress analyses. The P-T curve derived from the best estimate load analysis and a t / 8 deep ... continued below

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26 p.

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Dickson, T.L.; Bass, B.R. & McAfee, W.J. January 1, 1998.

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Description

Analyses were performed to determine the impact of weld residual stresses in a reactor pressure vessel (RPV) on (1) the generation of pressure temperature (P-T) curves required for maintaining specified fracture prevention margins during nuclear plant startup and shutdown, and (2) the conditional probability of vessel failure due to pressurized thermal shock (PTS) loading. The through wall residual stress distribution in an axially oriented weld was derived using measurements taken from a shell segment of a canceled RPV and finite element thermal stress analyses. The P-T curve derived from the best estimate load analysis and a t / 8 deep flaw, based on K{sub Ic}, was less limiting than the one derived from the current methodology prescribed in the ASME Boiler and Pressure Vessel Code. The inclusion of the weld residual stresses increased the conditional probability of cleavage fracture due to PTS loading by a factor ranging from 2 to 4.

Physical Description

26 p.

Notes

INIS; OSTI as DE98004935

Source

  • 1998 ASME/JSME joint pressure vessel and piping (PVP) conference, San Diego, CA (United States), 26-30 Jul 1998

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  • Other: DE98004935
  • Report No.: ORNL/CP--96684
  • Report No.: CONF-980708--
  • Office of Scientific & Technical Information Report Number: 654172
  • Archival Resource Key: ark:/67531/metadc712010

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  • January 1, 1998

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

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  • May 5, 2016, 8:49 p.m.

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Dickson, T.L.; Bass, B.R. & McAfee, W.J. The inclusion of weld residual stress in fracture margin assessments of embrittled nuclear reactor pressure vessels, article, January 1, 1998; Tennessee. (digital.library.unt.edu/ark:/67531/metadc712010/: accessed August 23, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.