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Benchmark Analysis of EBR-Ⅱ Shutdown Heat Removal Test-17 using of Plant Dynamics Analysis Code and Subchannel Analysis Code

机译:使用植物动力学分析代码和子通道分析代码对EBR-Ⅱ关机排热测试17进行基准分析

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IAEA's Coordinated Research Project (CRP) on Benchmark Analyses of Shutdown Heat Removal Test (SHRT) performed at the Experimental Breeder Reactor Ⅱ (EBR-Ⅱ) has been carried out since 2012. JAEA participated in this CRP and applied two analysis codes developed by JAEA to the SHRT-17, which was provided by ANL as a benchmark analysis problem simulating a protected loss of flow accident (PLOF). In this study, the system code Super-COPD was used to simulate thermal-hydraulics in core, upper and lower plenums, cold pool, two primary loops with pumps, and an IHX. As for the core, flow re-distribution and inter-subassembly heat transfer were considered by modeling all subassemblies as independent channels and inter-subassembly gap in the core barrel. The temperature distributions in instrumented subassembly XX09 and XX10 were simulated by using the subchannel analysis code ASFRE through setting its boundary conditions of the core inlet temperature, the flow rate of the subassembly and the heat flux across the wrapper tube at the quantities obtained by the system analysis. These results indicate that the two analysis codes reasonably predict the temperatures in the core and the flow rates of the primary loops and the subassemblies during PLOF.
机译:自2012年以来,已开展了国际原子能机构关于在实验种反应堆Ⅱ(EBR-Ⅱ)上进行的关机排热测试(SHRT)基准分析的协调研究项目(CRP)。JAEA参与了该CRP,并应用了JAEA制定的两个分析代码由ANL提供的SHRT-17作为基准分析问题,用于模拟受保护的流量损失事故(PLOF)。在这项研究中,系统代码Super-COPD用于模拟岩心,上部和下部气室,冷池,两个带泵的主回路和一个IHX中的热工液压。对于岩心,通过将所有子组件建模为岩心桶中的独立通道和子组件间的间隙,考虑了流量的重新分配和子组件间的传热。通过使用子通道分析代码ASFRE通过设置系统获得的数量的芯入口温度,子组件的流速和穿过封皮管的热通量的边界条件,使用子通道分析代码ASFRE模拟了仪表化子组件XX09和XX10中的温度分布。分析。这些结果表明,这两个分析代码可以合理地预测PLOF期间堆芯的温度以及主回路和子组件的流量。

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