Preliminary Risk Assessment Associated with IGSCC of BWR Vessel Internals

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Description

BWR core shrouds and other reactor internals important to safety are experiencing intergranular stress corrosion cracking (IGSCC). The United States Nuclear Regulatory Commission (NRC) has followed the problem, and as part of its investigations, contracted with the Idaho National Engineering and Environmental Laboratory (INEEL) to conduct a risk assessment. The overall project objective is to assess the potential consequences and risks associated with the failure of IGSCC-susceptible BWR vessel internals, with specific consideration given to potential cascading and common mode effects. The paper presents an overview of the program, discusses the results of a preliminary qualitative assessment, and summarizes a ... continued below

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9 p.

Creation Information

Ware, Arthur; Morton, Keith; Nitzel, Michael; Chokshi, Nilesh & Chang, Tsun-Yung August 1, 1999.

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This article is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. More information about this article can be viewed below.

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  • Ware, Arthur Corresponding Author; Idaho National Engineering and Environmental Laboratory (INEEL)
  • Morton, Keith Idaho National Engineering and Environmental Laboratory (INEEL)
  • Nitzel, Michael Idaho National Engineering and Environmental Laboratory (INEEL)
  • Chokshi, Nilesh United States. Nuclear Regulatory Commission.
  • Chang, Tsun-Yung United States. Nuclear Regulatory Commission.

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Description

BWR core shrouds and other reactor internals important to safety are experiencing intergranular stress corrosion cracking (IGSCC). The United States Nuclear Regulatory Commission (NRC) has followed the problem, and as part of its investigations, contracted with the Idaho National Engineering and Environmental Laboratory (INEEL) to conduct a risk assessment. The overall project objective is to assess the potential consequences and risks associated with the failure of IGSCC-susceptible BWR vessel internals, with specific consideration given to potential cascading and common mode effects. The paper presents an overview of the program, discusses the results of a preliminary qualitative assessment, and summarizes a simplified risk assessment that was conducted on sequences resulting from failures of jet pump components of a BWR/4 plant.

Physical Description

9 p.

Notes

INIS; OSTI as DE00008199

Medium: P; Size: 9 pages

Source

  • 15th Structural Mechanics in Reactor Technology Conference (SMiRT-15), Seoul (KR), 08/15/1999--08/20/1999

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  • Report No.: INEEL/CON-99-00264
  • Grant Number: AC07-94ID13223
  • Office of Scientific & Technical Information Report Number: 8199
  • Archival Resource Key: ark:/67531/metadc739324

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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, 11:32 a.m.

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Ware, Arthur; Morton, Keith; Nitzel, Michael; Chokshi, Nilesh & Chang, Tsun-Yung. Preliminary Risk Assessment Associated with IGSCC of BWR Vessel Internals, article, August 1, 1999; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc739324/: accessed August 20, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.