A Program for Risk Assessment Associated with IGSCC of BWR Vessel Internals

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Description

A program is being carried out for the US Nuclear Regulatory Commission (NRC) by the Idaho National Engineering and Environmental Laboratory (INEEL), to conduct an independent risk assessment of the consequences of failures initiated by intergranular stress corrosion cracking (IGSCC) of the reactor vessel internals of boiling water reactor (BWR) plants. The overall project objective is to assess the potential consequences and risks associated with the failure of IGSCC-susceptible BWR vessel internals, both singly and in combination with the failures of others, with specific consideration given to potential cascading and common mode effects on system performance. This paper presents a ... continued below

Physical Description

7 p.

Creation Information

Ware, Arthur G.; Morton, D. Keith; Page, Joel D.; Nitzel, Michael E.; Eide, Steven A. & Chang, T. -Y. August 1, 1999.

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  • Ware, Arthur G. Idaho National Engineering and Environmental Laboratory (INEEL)
  • Morton, D. Keith Idaho National Engineering and Environmental Laboratory (INEEL)
  • Page, Joel D. United States. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.
  • Nitzel, Michael E. Idaho National Engineering and Environmental Laboratory (INEEL)
  • Eide, Steven A. Idaho National Engineering and Environmental Laboratory (INEEL)
  • Chang, T. -Y. United States. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.

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Description

A program is being carried out for the US Nuclear Regulatory Commission (NRC) by the Idaho National Engineering and Environmental Laboratory (INEEL), to conduct an independent risk assessment of the consequences of failures initiated by intergranular stress corrosion cracking (IGSCC) of the reactor vessel internals of boiling water reactor (BWR) plants. The overall project objective is to assess the potential consequences and risks associated with the failure of IGSCC-susceptible BWR vessel internals, both singly and in combination with the failures of others, with specific consideration given to potential cascading and common mode effects on system performance. This paper presents a description of the overall program that is underway to modify an existing probabilistic risk assessment (PRA) of the BWR/4 plant to include IGSCC-initiated failures, subsequently to complete a quantitative PRA.

Physical Description

7 p.

Notes

INIS; OSTI as DE00008079

Medium: P; Size: 7 pages

Source

  • Pressure Vessels and Piping Conference, Boston, MA (US), 08/01/1999--08/04/1999

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Identifier

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  • Report No.: INEEL/CON-98-01263
  • Grant Number: AC07-94ID13223
  • Office of Scientific & Technical Information Report Number: 8079
  • Archival Resource Key: ark:/67531/metadc740255

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Creation Date

  • August 1, 1999

Added to The UNT Digital Library

  • Oct. 18, 2015, 6:40 p.m.

Description Last Updated

  • July 13, 2017, 11:29 a.m.

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Ware, Arthur G.; Morton, D. Keith; Page, Joel D.; Nitzel, Michael E.; Eide, Steven A. & Chang, T. -Y. A Program for Risk Assessment Associated with IGSCC of BWR Vessel Internals, article, August 1, 1999; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc740255/: accessed August 20, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.