H233 超臨界圧流体の過熱蒸気域における熱伝達特性(一般講演)

概要

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For the developments and designs of the supercritical water cooled reactor (SCWR) which is an advanced nuclear reactor, it is necessary to accurately estimate heat transfer to supercritical pressure water in the superheated vapor region. In this study, a numerical analysis is carried out using the commercial CFD code STAR-CD, and compared with the experimental data obtained under the superheated vapor region. HCFC22 is used as a test fluid, which flows upward in a uniformly heated vertical circular tube. The k-co model is selected as the turbulence model and the effect of property variation on heat transfer is investigated.
2010-10-29