Abstract
In the passive decay heat removal system in high-temperature gas-cooled reactor (HTGR), the decay heat is transferred from the reactor pressure vessel(RPV) to cooling panel by radiation and natural convection. The thermal-hydraulic analysis for 1/8 scale mockup experiment simulating passive decay heat removal system of HTGR was performed to demonstrate the numerical calculation accuracy on temperature of RPV. The 3-dimensional 30-deg. sector model which included heater, RPV and cooling panel, was created on analytical code FLUENT v6.3. The temperature on outer face of RPV was numerically calculated within the difference of 10℃ from the experiment data with the condition of helium pressure of 0.47MPa and 0.11MPa in RPV.
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