Nuclear energy plant optimization (NEPO) final scientific/technical report

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The overall objective of this 3 year research program has been to support the aging management programs for LWR reactors through the extended 60-year lifetimes by adding to the knowledge base of irradiation-induced effects on the mechanical properties and cracking resistance of stainless steel (SS) core components. Over the course of this project, efforts have focused on enhancing the understanding of the link between deformation and fracture behavior in work-hardened and irradiated stainless steels. This understanding is achieved through a combination of mechanical testing, microstructural characterization, and development of models to describe the observed behavior. The understanding gained provides a ... continued below

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Creation Information

Cole, J. I.; Daum, R. S.; Tsai, H.; Porter, D. L.; Allen, T. R. & Wirth, B. D. February 2, 2004.

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This report 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 report can be viewed below.

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  • Argonne National Laboratory
    Publisher Info: Argonne National Lab., Argonne, IL (United States)
    Place of Publication: Argonne, Illinois

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Description

The overall objective of this 3 year research program has been to support the aging management programs for LWR reactors through the extended 60-year lifetimes by adding to the knowledge base of irradiation-induced effects on the mechanical properties and cracking resistance of stainless steel (SS) core components. Over the course of this project, efforts have focused on enhancing the understanding of the link between deformation and fracture behavior in work-hardened and irradiated stainless steels. This understanding is achieved through a combination of mechanical testing, microstructural characterization, and development of models to describe the observed behavior. The understanding gained provides a foundation for evaluating the aging behavior of components during in-core service in terms of radiation embrittlement and alloy susceptibility to irradiation assisted stress corrosion cracking (IASCC).

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  • Other Information: PBD: 2 Feb 2004

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  • Report No.: ANL-03/34
  • Grant Number: W-31-109-ENG-38
  • DOI: 10.2172/834694 | External Link
  • Office of Scientific & Technical Information Report Number: 834694
  • Archival Resource Key: ark:/67531/metadc788778

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Creation Date

  • February 2, 2004

Added to The UNT Digital Library

  • Dec. 3, 2015, 9:30 a.m.

Description Last Updated

  • March 25, 2016, 1:58 p.m.

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Cole, J. I.; Daum, R. S.; Tsai, H.; Porter, D. L.; Allen, T. R. & Wirth, B. D. Nuclear energy plant optimization (NEPO) final scientific/technical report, report, February 2, 2004; Argonne, Illinois. (digital.library.unt.edu/ark:/67531/metadc788778/: accessed August 17, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.