Conclusions
An apparatus was developed for measuring the frictional characteristics and was tested during in-reactor experiments. Apparently, the significant increase in the coefficient of static friction observed during the in-reactor irradiation process must be considered when evaluating the stress (deformed) state of the fuel elements during power fluctuations (jumps), i. e., in case of power increase after relatively long-term operation at a low power.
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Translated from Atomnaya Énergiya, Vol. 61, No. 3, pp. 175–178, September, 1986.
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Shchavelin, V.M., Kostochka, A.V., Kuznetsov, A.A. et al. In-reactor study of the friction characteristics of reactor materials. At Energy 61, 686–690 (1986). https://doi.org/10.1007/BF01129870
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DOI: https://doi.org/10.1007/BF01129870