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2017 | 132 | 3 | 830-832
Article title

Assessment on Gamma Attenuation Behavior of W-VC-C and W-VC-TiC-C Composites for Co-60 Radioisotope

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Languages of publication
EN
Abstracts
EN
In this study, tungsten-vanadium carbide-graphite (W-VC-C) and tungsten-vanadium carbide-titanium carbide-graphite composite (W-VC-TiC-C) materials were investigated against Co-60 gamma radioisotope. The composite materials which are used in advanced technological studies and high temperature applications in many various fields especially in the areas of fission and fusion armor materials were produced by mechanical alloying method as in two groups. One of them include 93% tungsten (W), 6% vanadium carbide (VC) and 1% graphite (C) also which has three different alloying times (6-12-24 h). Other group of the samples was composed of 91% tungsten, 6% vanadium carbide (VC), 2% titanium carbide (TiC) and 1% graphite (C) also which has three different alloying times (6-12-24 h) and sintered at 1750°C. Co-60 gamma radioisotope source and gamma transmission technique were used in the experiments to investigate the properties of the composite materials. The mass attenuation coefficients of the samples were determined by using experimental results and theoretical mass attenuation coefficients were calculated from XCOM computer code. It can be concluded that increasing the tungsten ratio causes higher mass attenuation coefficient and the composite materials have provided us benefits better than lead for radiation gamma shielding.
Publisher

Year
Volume
132
Issue
3
Pages
830-832
Physical description
Dates
published
2017-09
Contributors
author
  • Istanbul Technical University, Energy Institute, Nuclear Researches Division, Ayazaga Campus, 34469, Sariyer, Istanbul, Turkey
author
  • Istanbul Technical University, Energy Institute, Nuclear Researches Division, Ayazaga Campus, 34469, Sariyer, Istanbul, Turkey
author
  • Istanbul Technical University, Particulate Materials Laboratories, Materials Science and Engineering Faculty, Ayazaga Campus, 34469, Sariyer, Istanbul, Turkey
author
  • Istanbul Technical University, Particulate Materials Laboratories, Materials Science and Engineering Faculty, Ayazaga Campus, 34469, Sariyer, Istanbul, Turkey
author
  • Istanbul Technical University, Energy Institute, Nuclear Researches Division, Ayazaga Campus, 34469, Sariyer, Istanbul, Turkey
author
  • Istanbul Technical University, Particulate Materials Laboratories, Materials Science and Engineering Faculty, Ayazaga Campus, 34469, Sariyer, Istanbul, Turkey
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Document Type
Publication order reference
Identifiers
YADDA identifier
bwmeta1.element.bwnjournal-article-app132z3-iip007kz
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