A Coolant Flow Simulation in Fast Reactor Wire-Wrapped Assembly

V. Yu. Volkov; O. V. Belova; A. A. Krutikov; A. P. Skibin

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A Coolant Flow Simulation in Fast Reactor Wire-Wrapped Assembly

机译：快速反应堆绕线组件中的冷却剂流动模拟

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A CFD model of a 19-rod wire-wrapped fuel assembly is developed. The effect the size of computation mesh in the calculated region and the type of turbulence models have on the pressure drop between the inlet to and outlet from the calculated region is investigated. The possibility of shifting from low-Reynolds to high-Reynolds turbulence models is substantiated. Such a shift allows the mesh size in the calculated region to be reduced by approximately a factor of 18. The obtained results are in good agreement with the empirical dependences and international calculations.

机译：建立了19杆绕线式燃料组件的CFD模型。研究了计算区域中计算网格的大小和湍流模型类型对计算区域的入口和出口之间的压降的影响。从低雷诺湍流模型转变为高雷诺湍流模型的可能性得到了证实。这样的偏移使计算区域中的网格尺寸减小了大约18倍。获得的结果与经验依赖性和国际计算都很好地吻合。

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来源
《Thermal engineering》 |2013年第6期|429-433|共5页
作者
V. Yu. Volkov; O. V. Belova; A. A. Krutikov; A. P. Skibin;
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作者单位

Bauman Moscow State Technical University, Vtoraya Baumanskaya ul. 5, Moscow, 105005 Russia;

Bauman Moscow State Technical University, Vtoraya Baumanskaya ul. 5, Moscow, 105005 Russia;

Bauman Moscow State Technical University, Vtoraya Baumanskaya ul. 5, Moscow, 105005 Russia;

Bauman Moscow State Technical University, Vtoraya Baumanskaya ul. 5, Moscow, 105005 Russia;

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原文格式 PDF
正文语种 eng
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关键词
fast reactor; wire wrapping; pins; computational fluid dynamics; low-Reynolds and high-Reynolds turbulence models; mesh;

机译：快速反应堆绕线;别针计算流体动力学;低雷诺和高雷诺湍流模型;啮合;

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2. Numerical investigation on vortex behavior in wire-wrapped fuel assembly for a sodium fast reactor [J] . Min Seop Song, Jae Ho Jeong, Eung Soo Kim Nuclear engineering and technology . 2019,第3期

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3. CFD investigation on thermal-hydraulic behaviors of a wire-wrapped fuel subassembly for sodium-cooled fast reactor [J] . Chen Jing, Zhang Dalin, Song Ping, Annals of nuclear energy . 2018,第MARa期

机译：CFD研究钠冷快堆用线绕式燃料组件的热工行为
4. RANS-based CFD Simulations of Wire-Wrapped Fast Reactor Fuel Assemblies [C] . W. David Pointer, Paul Fischer, Andrew Siegel, International conference on advances in nuclear power plants;ICAPP 2008 . 2008

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A Coolant Flow Simulation in Fast Reactor Wire-Wrapped Assembly

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