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Report No.

Numerical analysis of supercritical water flowing in an annular channel using the two-fluid model code ACE-3D

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

In order to confirm thermal safety of the supercritical-water-cooled reactor (SCWR), it is important to assess the thermal hydraulics in rod bundles of the core. In the present study, the three-dimensional two-fluid model analysis code ACE-3D, which has been developed in JAEA for the two-phase flow thermal-hydraulics of light water reactors, was improved to handle the thermal hydraulic properties of water at supercritical region. Heat transfer experiments of supercritical water flowing in a vertical annular channel around a heater pin, which simulates core flow around a fuel rod, were analyzed with the ACE-3D to assess the prediction performance of the code. As a result, it was confirmed that the calculated wall surface temperature agreed with the measured results and the code is applicable to prediction of heat transfer of supercritical water in the system that simulates the SCWR core. To improve prediction accuracy for heat transfer deterioration is a subject for future study.



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