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Analysis of graphite-paraffin composite in neutron radiography, impact resistance, and thermal neutron attenuation.

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Title: Analysis of graphite-paraffin composite in neutron radiography, impact resistance, and thermal neutron attenuation.
Authors: Mohamad Fahmi, Adam Haziq1 (AUTHOR), Sazali, Muhammad Arif1 (AUTHOR) muhammadarifsazali@utm.my, Yazid, Khairiah2 (AUTHOR), Abu Bakar, Asyraf Arif2 (AUTHOR), Mohd Ali, Nur Syazwani1 (AUTHOR), Jamaluddin, Khairulnadzmi1 (AUTHOR), Sarkawi, Muhammad Syahir1 (AUTHOR)
Source: Radiation Physics & Chemistry. May2024, Vol. 218, pN.PAG-N.PAG. 1p.
Subjects: Neutron radiography, Research reactors, Thermal neutrons, Neutron capture, Impact testing, Graphite
Abstract: In this study, samples of paraffin-graphite composite were prepared to evaluate the effects of graphite on the impact resistance and neutron attenuation of the composite. This is to address the need for novel-formulated polymers for radiation surveying robots that can withstand radiation effects while having good mechanical properties. The composite samples were made using the melt-mixing method. An Izod impact test based on the ASTM D256 standard was carried out to measure the toughness of the composite. The results suggest that increasing the graphite content from 1 wt% to 5 wt% decreases the composite's impact resistance. 3 mm-thick samples were also examined using neutron radiography at the TRIGA Mk-II research reactor in the Malaysian Nuclear Agency. The grey values in the line profile show an increasing trend with increasing graphite content, indicating decreased thermal neutron absorption/removal. Unseen cracks were also identified in the neutron image. The shielding performance was evaluated using attenuation experiments at two different thicknesses. The results reveal that adding graphite to paraffin can improve its neutron shielding capability up to certain weight percentages. Increasing the graphite content further than 3 wt% caused an increase in neutron transmission, likely due to the buildup effect. The impact resistance of the composite is higher than that of pure paraffin. However, the resistance decreases with graphite content. Overall, the most optimal formulation in the context of this study in terms of impact resistance and neutron shielding performance was paraffin+2 wt% graphite. • 1–5 wt% graphite was added to a paraffin-based composite. • Increasing amount of graphite results in decreasing impact resistance. • 2–3 wt% graphite showed the lowest neutron dose rates. [ABSTRACT FROM AUTHOR]
Copyright of Radiation Physics & Chemistry is the property of Pergamon Press - An Imprint of Elsevier Science 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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DbLabel: Engineering Source
An: 176036905
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PubType: Academic Journal
PubTypeId: academicJournal
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  Data: Analysis of graphite-paraffin composite in neutron radiography, impact resistance, and thermal neutron attenuation.
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  Data: <searchLink fieldCode="AR" term="%22Mohamad+Fahmi%2C+Adam+Haziq%22">Mohamad Fahmi, Adam Haziq</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Sazali%2C+Muhammad+Arif%22">Sazali, Muhammad Arif</searchLink><relatesTo>1</relatesTo> (AUTHOR)<i> muhammadarifsazali@utm.my</i><br /><searchLink fieldCode="AR" term="%22Yazid%2C+Khairiah%22">Yazid, Khairiah</searchLink><relatesTo>2</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Abu+Bakar%2C+Asyraf+Arif%22">Abu Bakar, Asyraf Arif</searchLink><relatesTo>2</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Mohd+Ali%2C+Nur+Syazwani%22">Mohd Ali, Nur Syazwani</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Jamaluddin%2C+Khairulnadzmi%22">Jamaluddin, Khairulnadzmi</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Sarkawi%2C+Muhammad+Syahir%22">Sarkawi, Muhammad Syahir</searchLink><relatesTo>1</relatesTo> (AUTHOR)
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  Data: <searchLink fieldCode="JN" term="%22Radiation+Physics+%26+Chemistry%22">Radiation Physics & Chemistry</searchLink>. May2024, Vol. 218, pN.PAG-N.PAG. 1p.
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  Data: <searchLink fieldCode="DE" term="%22Neutron+radiography%22">Neutron radiography</searchLink><br /><searchLink fieldCode="DE" term="%22Research+reactors%22">Research reactors</searchLink><br /><searchLink fieldCode="DE" term="%22Thermal+neutrons%22">Thermal neutrons</searchLink><br /><searchLink fieldCode="DE" term="%22Neutron+capture%22">Neutron capture</searchLink><br /><searchLink fieldCode="DE" term="%22Impact+testing%22">Impact testing</searchLink><br /><searchLink fieldCode="DE" term="%22Graphite%22">Graphite</searchLink>
– Name: Abstract
  Label: Abstract
  Group: Ab
  Data: In this study, samples of paraffin-graphite composite were prepared to evaluate the effects of graphite on the impact resistance and neutron attenuation of the composite. This is to address the need for novel-formulated polymers for radiation surveying robots that can withstand radiation effects while having good mechanical properties. The composite samples were made using the melt-mixing method. An Izod impact test based on the ASTM D256 standard was carried out to measure the toughness of the composite. The results suggest that increasing the graphite content from 1 wt% to 5 wt% decreases the composite's impact resistance. 3 mm-thick samples were also examined using neutron radiography at the TRIGA Mk-II research reactor in the Malaysian Nuclear Agency. The grey values in the line profile show an increasing trend with increasing graphite content, indicating decreased thermal neutron absorption/removal. Unseen cracks were also identified in the neutron image. The shielding performance was evaluated using attenuation experiments at two different thicknesses. The results reveal that adding graphite to paraffin can improve its neutron shielding capability up to certain weight percentages. Increasing the graphite content further than 3 wt% caused an increase in neutron transmission, likely due to the buildup effect. The impact resistance of the composite is higher than that of pure paraffin. However, the resistance decreases with graphite content. Overall, the most optimal formulation in the context of this study in terms of impact resistance and neutron shielding performance was paraffin+2 wt% graphite. • 1–5 wt% graphite was added to a paraffin-based composite. • Increasing amount of graphite results in decreasing impact resistance. • 2–3 wt% graphite showed the lowest neutron dose rates. [ABSTRACT FROM AUTHOR]
– Name: AbstractSuppliedCopyright
  Label:
  Group: Ab
  Data: <i>Copyright of Radiation Physics & Chemistry is the property of Pergamon Press - An Imprint of Elsevier Science 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:
  BibEntity:
    Identifiers:
      – Type: doi
        Value: 10.1016/j.radphyschem.2024.111639
    Languages:
      – Code: eng
        Text: English
    PhysicalDescription:
      Pagination:
        PageCount: 1
        StartPage: N.PAG
    Subjects:
      – SubjectFull: Neutron radiography
        Type: general
      – SubjectFull: Research reactors
        Type: general
      – SubjectFull: Thermal neutrons
        Type: general
      – SubjectFull: Neutron capture
        Type: general
      – SubjectFull: Impact testing
        Type: general
      – SubjectFull: Graphite
        Type: general
    Titles:
      – TitleFull: Analysis of graphite-paraffin composite in neutron radiography, impact resistance, and thermal neutron attenuation.
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            NameFull: Mohamad Fahmi, Adam Haziq
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            NameFull: Sazali, Muhammad Arif
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            NameFull: Yazid, Khairiah
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          Dates:
            – D: 01
              M: 05
              Text: May2024
              Type: published
              Y: 2024
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              Value: 0969806X
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              Value: 218
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            – TitleFull: Radiation Physics & Chemistry
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