Combined Numerical and Experimental Investigations of Local Hydrodynamics and Coolant Flow Mass Transfer in Kvadrat-Type Fuel Assemblies of PWR Reactors with Mixing Grids

S. M. Dmitriev; O. B. Samoilov; A. E. Khrobostov; A. V. Varentsov; A. A. Dobrov; D. V. Doronkov; V. D. Sorokin

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Combined Numerical and Experimental Investigations of Local Hydrodynamics and Coolant Flow Mass Transfer in Kvadrat-Type Fuel Assemblies of PWR Reactors with Mixing Grids

机译：带有混合网格的压水堆反应堆Kvadrat型燃料组件中局部流体动力学和冷却剂流量传质的组合数值和实验研究

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摘要

Results of research works on studying local hydrodynamics and mass transfer for coolant flow in the characteristic zones of PWR reactor fuel assemblies in case of using belts of mixing spacer grids are presented. The investigations were carried out on an aerodynamic rig using the admixture diffusion method (the tracer-gas method). Certain specific features pertinent to coolant flow in the fuel rod bundles of Kvadrat-type fuel assemblies were revealed during the experiments. The obtained study results were included in the database for verifying computation fluid dynamics computer codes and detailed cell-wise calculations of reactor cores with Kvadrat-type fuel assemblies. The obtained results can also be used for more exact determination of local coolant flow hydrodynamic and mass transfer characteristics in assessing thermal reliability of PWR reactor cores.

机译：给出了在使用混合间隔栅带的情况下研究压水堆反应堆燃料组件特征区域中的冷却剂流动的局部流体动力学和传质的研究结果。使用混合扩散法（示踪气体法）在气动设备上进行了研究。实验期间揭示了与冷却液在Kvadrat型燃料组件的燃料棒束中流动有关的某些特定特征。所获得的研究结果已包括在数据库中，以验证计算流体力学计算机代码和具有Kvadrat型燃料组件的反应堆堆芯的详细逐单元计算。获得的结果还可以用于评估PWR反应堆堆芯的热可靠性时更精确地确定局部冷却剂流量的流体动力学和传质特性。

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来源
《Thermal engineering》 |2014年第8期|558-565|共8页
作者
S. M. Dmitriev; O. B. Samoilov; A. E. Khrobostov; A. V. Varentsov; A. A. Dobrov; D. V. Doronkov; V. D. Sorokin;
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作者单位

Alekseev Nizhny Novgorod State Technical University, ul. Minina 24, Nizhny Novgorod, 603950 Russia;

Afrikantov Experimental Design Office for Mechanical Engineering, Burnakovskii pr. 15, Nizhny Novgorod, 603074 Russia;

Alekseev Nizhny Novgorod State Technical University, ul. Minina 24, Nizhny Novgorod, 603950 Russia;

Alekseev Nizhny Novgorod State Technical University, ul. Minina 24, Nizhny Novgorod, 603950 Russia;

Alekseev Nizhny Novgorod State Technical University, ul. Minina 24, Nizhny Novgorod, 603950 Russia;

Alekseev Nizhny Novgorod State Technical University, ul. Minina 24, Nizhny Novgorod, 603950 Russia;

Alekseev Nizhny Novgorod State Technical University, ul. Minina 24, Nizhny Novgorod, 603950 Russia;

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正文语种 eng
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关键词
nuclear reactor; fuel assembly; coolant hydrodynamics; interchannel mass transfer; mixing spacer grid;

机译：核反应堆;燃料组件;冷却液流体动力学;通道间传质混合隔栅;

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1. Combined numerical and experimental investigation into the coolant flow hydrodynamics and mass transfer behind the spacer grid in fuel assemblies of the floating power unit reactor [J] . S.M. Dmitriev, D.V. Doronkov, A.N. Pronin, Nuclear Energy and Technology . 2015,第1期

机译：浮式动力装置反应堆燃料组件中隔栅后面的冷却液流动流体力学和传质的数值和实验研究相结合
2. Experimental study of local coolant hydrodynamics in TVS-Kvadrat PWR reactor fuel assembly using mixing spacer grids with different types of deflectors [J] . S.M. Dmitriev, S.S. Borodin, A.V. Varentsov, Nuclear Energy and Technology . 2015,第4期

机译：TVS-Kvadrat PWR反应堆燃料组件中使用不同类型偏转器的混合间隔栅进行局部冷却剂流体动力学的实验研究
3. Studying the Swirl Flow Hydrodynamics in the Guiding Channel Area Downstream of Mixing Spacer Grids of a PWR Reactor Fuel Assembly [J] . S. M. Dmitriev, A. V. Gerasimov, A. A. Dobrov, Thermal engineering . 2021,第3期

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4. Local Hydrodynamics and Mass-transfer of Coolant in VVER-1000 FA with Mixing Grids [C] . Dmitriev Sergey, Borodin Sergey, Legchanov Maxim, 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety. . 2010

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7. Combined numerical and experimental investigation into the coolant flow hydrodynamics and mass transfer behind the spacer grid in fuel assemblies of the floating power unit reactor [O] . S.M. Dmitriev, D.V. Doronkov, A.N. Pronin, 2015

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Combined Numerical and Experimental Investigations of Local Hydrodynamics and Coolant Flow Mass Transfer in Kvadrat-Type Fuel Assemblies of PWR Reactors with Mixing Grids

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