首页> 外文会议>International topical meeting on nuclear reactor thermal hydraulics >PSEUDO 3-D FULL-CORE CONJUGATE HEAT TRANSFER MODELING OF SODIUM FAST REACTORS
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PSEUDO 3-D FULL-CORE CONJUGATE HEAT TRANSFER MODELING OF SODIUM FAST REACTORS

机译:Pseudo 3-D全核共轭热转移型钠快速反应器

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For efficient and accurate temperature predictions of sodium fast reactor structures, a 3-D full-core conjugate heat transfer modeling capability is developed for an advanced system analysis tool, SAM. The hexagon lattice core is modeled with 1-D parallel channels representing the subassembly flow, and 2-D duct walls and inter-assembly gaps. The six sides of the hexagon duct wall are modeled separately to account for different temperatures and heat transfer between inner assembly flow and each side of the duct wall. The Jacobian Free Newton Krylov (JFNK) solution method is applied to solve the fluid and solid field simultaneously in a fully coupled fashion. The 3-D full-core conjugate heat transfer modeling capability in SAM has been demonstrated by a verification test problem with 7 fuel assemblies in a hexagon lattice layout. Additionally, the simulation results are compared with RANS-based CFD simulations. Very good agreements have been achieved between the results of the two approaches.
机译:对于快速反应器结构的高效和准确温度预测,为先进的系统分析工具,SAM开发了3D全核共轭传热建模能力。六边形晶格芯采用1-D并联通道,表示子组件流动,2-D管壁和组装间隙。六边形管壁的六个侧面被单独建模,以考虑不同温度和内部组件流动与管道壁的每一侧之间的传热。雅各比比牛顿Krylov(JFNK)解决方案方法应用于以完全耦合的方式同时解决流体和实地。 SAM中的3-D全核共轭传热建模能力通过六边形格子布局中的7个燃料组件进行了验证测试问题。另外,将仿真结果与基于RAN的CFD模拟进行了比较。两种方法的结果之间已经实现了非常好的协议。

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