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Irradiation effects on graphite foam

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Title: Irradiation effects on graphite foam
Authors: Gallego, Nidia C. gallegonc@ornl.gov, Burchell, Timothy D.1, Klett, James W.1
Source: Carbon. Apr2006, Vol. 44 Issue 4, p618-628. 11p.
Subjects: Irradiation, Heat transfer, Graphite, Foam, Thermal properties
Abstract: Abstract: The solid state reactor is an advanced reactor concept that takes advantage of newly developed materials with enhanced heat transfer characteristics to provide an inherently safe, self-regulated heat source. High conductivity graphite foam, developed and produced at Oak Ridge National Laboratory, is being evaluated as a candidate material for the core of basic heat source modules. Irradiation studies at the Oak Ridge National Laboratory High Flux Isotope Reactor were conducted to obtain preliminary data on the effects of neutron damage on the thermal properties and volume change behavior of the graphite foam as a function of neutron dose up to 2.6 displacements per atom at an irradiation temperature of ∼740°C. Samples were characterized for dimensional and structural changes, and thermal transport as a function of dose. Following the initial effects of the irradiation, the samples were annealed at 1000 and 1200°C and the thermal diffusivity measured as a function of temperature. A simple microstructural model was developed for graphite foam and, by coupling this model to the known single crystal and polycrystalline irradiation behavior of graphite; a mechanism by which the irradiation-induced volume and dimensional changes in graphite foam may be explained is postulated. [Copyright &y& Elsevier]
Copyright of Carbon is the property of Elsevier B.V. and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
Database: Engineering Source
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Header DbId: egs
DbLabel: Engineering Source
An: 19307077
AccessLevel: 6
PubType: Academic Journal
PubTypeId: academicJournal
PreciseRelevancyScore: 0
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  Data: Irradiation effects on graphite foam
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  Data: <searchLink fieldCode="AR" term="%22Gallego%2C+Nidia+C%2E%22">Gallego, Nidia C.</searchLink><i> gallegonc@ornl.gov</i><br /><searchLink fieldCode="AR" term="%22Burchell%2C+Timothy+D%2E%22">Burchell, Timothy D.</searchLink><relatesTo>1</relatesTo><br /><searchLink fieldCode="AR" term="%22Klett%2C+James+W%2E%22">Klett, James W.</searchLink><relatesTo>1</relatesTo>
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  Data: <searchLink fieldCode="JN" term="%22Carbon%22">Carbon</searchLink>. Apr2006, Vol. 44 Issue 4, p618-628. 11p.
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  Data: <searchLink fieldCode="DE" term="%22Irradiation%22">Irradiation</searchLink><br /><searchLink fieldCode="DE" term="%22Heat+transfer%22">Heat transfer</searchLink><br /><searchLink fieldCode="DE" term="%22Graphite%22">Graphite</searchLink><br /><searchLink fieldCode="DE" term="%22Foam%22">Foam</searchLink><br /><searchLink fieldCode="DE" term="%22Thermal+properties%22">Thermal properties</searchLink>
– Name: Abstract
  Label: Abstract
  Group: Ab
  Data: Abstract: The solid state reactor is an advanced reactor concept that takes advantage of newly developed materials with enhanced heat transfer characteristics to provide an inherently safe, self-regulated heat source. High conductivity graphite foam, developed and produced at Oak Ridge National Laboratory, is being evaluated as a candidate material for the core of basic heat source modules. Irradiation studies at the Oak Ridge National Laboratory High Flux Isotope Reactor were conducted to obtain preliminary data on the effects of neutron damage on the thermal properties and volume change behavior of the graphite foam as a function of neutron dose up to 2.6 displacements per atom at an irradiation temperature of ∼740°C. Samples were characterized for dimensional and structural changes, and thermal transport as a function of dose. Following the initial effects of the irradiation, the samples were annealed at 1000 and 1200°C and the thermal diffusivity measured as a function of temperature. A simple microstructural model was developed for graphite foam and, by coupling this model to the known single crystal and polycrystalline irradiation behavior of graphite; a mechanism by which the irradiation-induced volume and dimensional changes in graphite foam may be explained is postulated. [Copyright &y& Elsevier]
– Name: AbstractSuppliedCopyright
  Label:
  Group: Ab
  Data: <i>Copyright of Carbon is the property of Elsevier B.V. and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.)
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RecordInfo BibRecord:
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      – Type: doi
        Value: 10.1016/j.carbon.2005.09.038
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      – Code: eng
        Text: English
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      Pagination:
        PageCount: 11
        StartPage: 618
    Subjects:
      – SubjectFull: Irradiation
        Type: general
      – SubjectFull: Heat transfer
        Type: general
      – SubjectFull: Graphite
        Type: general
      – SubjectFull: Foam
        Type: general
      – SubjectFull: Thermal properties
        Type: general
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      – TitleFull: Irradiation effects on graphite foam
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            NameFull: Gallego, Nidia C.
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            NameFull: Burchell, Timothy D.
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              M: 04
              Text: Apr2006
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              Y: 2006
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