Computational-experimental determination of the temperature of the components of a shipping container with spent fuel |
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Authors: | A V Kudryavtsev E A Ovsyannikova |
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Affiliation: | (1) Federal Nuclear Center-All-Russia Research Institute of Technical Physics, Russia |
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Abstract: | The results of a determination of the expected temperatures of the structural components of the container with long-term dry
storage and shipment of spent nuclear fuel from the AMB reactors at the Beloyarakaya nuclear power plant, under normal and
accident conditions, are presented. The requirements for its thermalprotection characteristics are formulated on the basis
of normative-technical documentation, and the basic assumptions and initial prerequisites, used to perform the calculations,
are presented. The computational-experimental method is used together with the results of tests performed on a prototype model
to confirm the possibility of ensuring the required temperatures of the basic components of the container and the fuel assembly.
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Translated from Atomnaya énergiya, Vol. 100, No. 6, pp. 428–431, June, 2006. |
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