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Heat transfer in a seven-rod test bundle with supercritical pressure water, 2; Numerical simulation

Misawa, Takeharu; Nakatsuka, Toru; Yoshida, Hiroyuki ; Takase, Kazuyuki

Japan Atomic Energy Agency (JAEA) has been enhancing the three-dimensional two-fluid model analysis code ACE-3D, which has been originally developed for the thermal design procedure on two-phase flow thermal-hydraulics of light water reactors, to predict thermal hydraulics characteristics of the supercritical water-cooled nuclear energy system under operation and transient conditions. To verify the prediction performance of the ACE-3D code, numerical analyses have been performed based on some experimental data. As a part of these verifications, a present paper describes the predicted results of seven-rod bundle heat transfer experiments with supercritical pressure water performed at JAEA. As a result, the calculated wall temperatures on the surface of simulated fuel rods were in agreement with the experimental results. One of future subjects is important in the prediction accuracy on the heat transfer deterioration.

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