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Testing of polysulfone for applications in nuclear facilities

✍ Scribed by V. Plaček; V. Hnát; R. Pejša; T. Kohout


Publisher
John Wiley and Sons
Year
2008
Tongue
English
Weight
227 KB
Volume
109
Category
Article
ISSN
0021-8995

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✦ Synopsis


Abstract

Polysulfone Tecason S samples, designed for use in nuclear facilities, were aged under different conditions to simulate their long‐term use in nuclear power plants. The specimens, with thicknesses of 4 mm, were irradiated with ^60^Co γ rays in oxygen and/or in air at different temperatures and thermally aged at 180°C. For all samples, the glass‐transition temperature, the stepwise change in the heat capacity at the glass‐transition temperature, and the oxidative induction temperature were measured with differential scanning calorimetry. Simultaneously, the mechanical properties were determined and correlated with the results obtained by differential scanning calorimetry. Although the material was aged under very harsh conditions (irradiation in oxygen with absorbed doses up to 500 kGy and thermal aging at 180°C up to 115 days), the detected changes were relatively small. Nevertheless, a tendency of the glass‐transition temperature and oxidative induction temperature to decrease with advanced material degradation was evident. The color changes of the cross‐sectional slices of some samples clearly indicated that the degradation was due to diffusion‐limited oxidation not homogeneously distributed throughout the sample bulk. In addition, samples from the near surface layers and from the center of the sample were examined. © 2008 Wiley Periodicals, Inc. J Appl Polym Sci, 2008


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