Abstract The Korea Atomic Energy Research Institute (KAERI) has developed the Core Reliable Optimization and thermofluid Network Analysis (CORONA) code for core thermofluid analysis of a prismatic high-temperature gas-cooled reactor (HTGR). KAERI performed scaled-down standard fuel block (SFB) heated tests at a helium experimental loop to validate the CORONA code. The scaled-down SFB was designed based on the core thermofluid design for a 350-MW(thermal) HTGR. The reference test condition was selected to maintain the Reynolds number of the coolant channels and the bypass gaps. The test section had seven coolant holes and 12 fuel holes considering KAERI’s helium loop circulator design. The material of the fuel block was Al2O3, selected to simulate the low thermal conductivity of the irradiated graphite at the high-temperature condition. The bypass gap structure was made of stainless steel 304 to minimize gap size deformation at the heated condition. This paper presents a comparison between the test results and the CORONA analysis results. The test parameter was the nitrogen flow velocity (3.6 to 6.0 kg/min) and constant heated condition.

中文翻译：

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统一加热按比例缩小的标准燃料块测试，以验证棱柱气冷反应堆的堆芯热流体分析代码

摘要 韩国原子能研究院 (KAERI) 开发了用于棱柱形高温气冷堆 (HTGR) 堆芯热流体分析的堆芯可靠性优化和热流体网络分析 (CORONA) 代码。KAERI 在氦实验回路中进行了按比例缩小的标准燃料块 (SFB) 加热测试，以验证 CORONA 代码。缩小的 SFB 是基于 350 MW（热）HTGR 的核心热流体设计而设计的。选择参考测试条件以保持冷却剂通道和旁路间隙的雷诺数。考虑到 KAERI 的氦回路循环器设计，测试部分有 7 个冷却剂孔和 12 个燃料孔。燃料块的材料是 Al2O3，选择以模拟高温条件下辐照石墨的低热导率。旁路间隙结构由不锈钢 304 制成，以最大限度地减少加热条件下的间隙尺寸变形。本文将测试结果与 CORONA 分析结果进行比较。测试参数是氮气流速（3.6 至 6.0 kg/min）和恒定加热条件。