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Number of results
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

Content

Title variants

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.

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

References

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Document Type

Publication order reference

Identifiers

YADDA identifier

bwmeta1.element.bwnjournal-article-app132z3-iip007kz
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