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Preliminary data on processing and characterization of recycled irradiated graphite

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Title: Preliminary data on processing and characterization of recycled irradiated graphite
Authors: Pappano, Peter J.1, Burchell, Timothy D. burchelltd@ornl.gov
Source: Carbon. Sep2010, Vol. 48 Issue 11, p3303-3305. 3p.
Subjects: Graphite, Filler materials, Feasibility studies, Particle size distribution, Radiology, Temperature effect
Abstract: Abstract: Neutron irradiated graphite was recycled as the “filler” material in reconstituted graphite. The work, performed in a radiological facility at the Oak Ridge National Laboratory, is believed to be the first ever demonstration of the feasibility of recycling irradiated graphite. The recycled graphite was lower in selected properties than commercially available nuclear graphite, but it is believed that similar property values could have been achieved with an impregnation step and a refined particle size distribution. The irradiation temperature and fluence of the graphites that were recycled had no discernable impact on the properties of the graphites made from them. [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: 51811862
AccessLevel: 6
PubType: Academic Journal
PubTypeId: academicJournal
PreciseRelevancyScore: 0
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  Data: Preliminary data on processing and characterization of recycled irradiated graphite
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  Data: <searchLink fieldCode="AR" term="%22Pappano%2C+Peter+J%2E%22">Pappano, Peter J.</searchLink><relatesTo>1</relatesTo><br /><searchLink fieldCode="AR" term="%22Burchell%2C+Timothy+D%2E%22">Burchell, Timothy D.</searchLink><i> burchelltd@ornl.gov</i>
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  Data: <searchLink fieldCode="JN" term="%22Carbon%22">Carbon</searchLink>. Sep2010, Vol. 48 Issue 11, p3303-3305. 3p.
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  Data: <searchLink fieldCode="DE" term="%22Graphite%22">Graphite</searchLink><br /><searchLink fieldCode="DE" term="%22Filler+materials%22">Filler materials</searchLink><br /><searchLink fieldCode="DE" term="%22Feasibility+studies%22">Feasibility studies</searchLink><br /><searchLink fieldCode="DE" term="%22Particle+size+distribution%22">Particle size distribution</searchLink><br /><searchLink fieldCode="DE" term="%22Radiology%22">Radiology</searchLink><br /><searchLink fieldCode="DE" term="%22Temperature+effect%22">Temperature effect</searchLink>
– Name: Abstract
  Label: Abstract
  Group: Ab
  Data: Abstract: Neutron irradiated graphite was recycled as the “filler” material in reconstituted graphite. The work, performed in a radiological facility at the Oak Ridge National Laboratory, is believed to be the first ever demonstration of the feasibility of recycling irradiated graphite. The recycled graphite was lower in selected properties than commercially available nuclear graphite, but it is believed that similar property values could have been achieved with an impregnation step and a refined particle size distribution. The irradiation temperature and fluence of the graphites that were recycled had no discernable impact on the properties of the graphites made from them. [Copyright &y& Elsevier]
– Name: AbstractSuppliedCopyright
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  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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        Value: 10.1016/j.carbon.2010.05.012
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        Text: English
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      – SubjectFull: Filler materials
        Type: general
      – SubjectFull: Feasibility studies
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      – SubjectFull: Particle size distribution
        Type: general
      – SubjectFull: Radiology
        Type: general
      – SubjectFull: Temperature effect
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      – TitleFull: Preliminary data on processing and characterization of recycled irradiated graphite
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