Subchannel analysis of thermal-hydraulic performance in rod bundle with spacer grid considering anisotropic turbulent mixing

2021 ◽  
Vol 167 ◽  
pp. 107039
Author(s):  
Zhenzhong Li ◽  
Deqi Chen ◽  
Dan Wu ◽  
Sufang Xin ◽  
Xiang Li
Keyword(s):  
Turbulent Mixing ◽  
Hydraulic Performance ◽  
Spacer Grid ◽  
Rod Bundle ◽  
Subchannel Analysis

scholarly journals OS8-3 Feasibility Study on Thermal-Hydraulic Performance in Tight-Lattice Rod Bundles (1) : 37-rod bundle tests and subchannel analysis

2006 ◽  
Vol 2006.11 (0) ◽  
pp. 195-196 ◽  
Author(s):  
Hidesada Tamai ◽  
Masatoshi Kureta ◽  
Akira Ohnuki ◽  
Hiroyuki Yoshida ◽  
Takashi Sato ◽  
...  
Keyword(s):  
Feasibility Study ◽  
Hydraulic Performance ◽  
Rod Bundles ◽  
Rod Bundle ◽  
Tight Lattice ◽  
Subchannel Analysis

Numerical investigation on thermal-hydraulic performance in 7×7 rod bundle with spacer grid and guide tubes

2021 ◽  
Vol 160 ◽  
pp. 106675
Author(s):  
Jin Lei ◽  
Shanshan Bu ◽  
Junze Jiang ◽  
Hanzhou Liu ◽  
Dewen Yuan ◽  
...  
Keyword(s):  
Numerical Investigation ◽  
Hydraulic Performance ◽  
Spacer Grid ◽  
Rod Bundle

Simulation of turbulent mixing rate in simulated subchannels of a reactor rod bundle

Kerntechnik ◽  
2021 ◽  
Vol 86 (3) ◽  
pp. 210-216
Author(s):  
M. P. Sharma ◽  
A. Moharana
Keyword(s):  
Turbulent Flows ◽  
Turbulent Mixing ◽  
Flow Behavior ◽  
Three Dimensional ◽  
Reynolds Stress Model ◽  
Momentum Equation ◽  
Mixing Rate ◽  
Mixing Coefficient ◽  
Rod Bundle ◽  
Subchannel Analysis

Abstract Subchannel analysis codes are widely used for the thermal-hydraulic design of nuclear reactor rod bundle. The effectiveness of subchannel analysis codes depends on turbulent mixing between these subchannels. Turbulent mixing has no direct contribution to the axial mass flow rate through subchannel but it will cause exchange of momentum and energy between the neighboring subchannels. Thus, it is important to evaluate the turbulent mixing coefficient for reactor rod bundle as it is a significant factor in the lateral energy and momentum equation for subchannel analysis codes like COBRA IIIC, COBRA-IV and MATRA LMR-FB. With the rapid developments in computational fluid dynamics and computer performance, three-dimensional analyses of turbulent flows occurring in the nuclear rod bundle have become more prominent. Several numerical analyses have already been attempted to investigate the flow behavior in rod bundles of different reactors. Much of these are dedicated to find out the structure of turbulence in rod bundle but a few analyses has been done to evaluate the magnitude of the turbulent mixing coefficient. In view of this, CFD analyses were carried out to determine the turbulent mixing coefficient in the simulated sub-channels of the reactor rod bundle. Previous studies on the structure of turbulence reveals that it is highly anisotropic. Hence, the Reynolds Stress Model (RSM), finer mesh and near wall distance ( y + ≤ 2) is required to capture turbulent mixing phenomena. The validation of results is done by comparing with subchannel mixing experiments.

Thermal–hydraulic performance of a 5 × 5 rod bundle with spacer grid in a nuclear reactor

2016 ◽  
Vol 103 ◽  
pp. 1416-1426 ◽  
Author(s):  
Deqi Chen ◽  
Yi Xiao ◽  
Shijie Xie ◽  
Dewen Yuan ◽  
Xuemei Lang ◽  
...  
Keyword(s):  
Nuclear Reactor ◽  
Hydraulic Performance ◽  
Spacer Grid ◽  
Rod Bundle

Flow and Temperature Fields Measurement Inside Rod Bundle by the Combined Use of PIV and LIF Technique

2018 ◽  
Author(s):  
Xing Li ◽  
Sichao Tan ◽  
Zhengpeng Mi ◽  
Peiyao Qi ◽  
Yunlong Huang
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Great Influence ◽  
Reactor Core ◽  
Transfer Characteristic ◽  
Index Of Refraction ◽  
Temperature Fields ◽  
Spacer Grid ◽  
Rod Bundle ◽  
Combined Use

Thermal hydraulic research of reactor core is important in nuclear energy applications, the flow and heat transfer characteristics of coolant in reactor fuel assembly has a great influence on the performance and safety of nuclear power plants. Particle image velocimetry (PIV) and Laser induced fluorescence (LIF) are the instantaneous, non-intrusive, whole-field fluid mechanics measuring method. In this study, the simultaneous measurement of flow field and temperature field for a rod bundle was conducted using PIV and LIF technique. A facility system, utilizing the matching index of refraction approach, has been designed and constructed for the measurement of velocity and temperature in the rod bundle. In order for further study on complex heat and mass transfer characteristic of rod bundle, the single-phase experiments on the heating conditions are performed. One of unique characteristics of the velocity and temperature distribution downstream the spacer grid was obtained. The experimental results show that the combined use of PIV and LIF technique is applied to the measurement of multi-physical field in a rod bundle is feasible, the measuring characteristics of non-intrusive ensured accuracy of whole field data. The whole field experimental data obtained in rod bundle benefits the design of spacer grid geometry.

Convergence study and uncertainty quantification of average and statistical PIV measurements in a matched refractive index 5×5 rod bundle with mixing vane spacer grid

2019 ◽  
Vol 102 ◽  
pp. 215-231 ◽  
Author(s):  
André Augusto Campagnole dos Santos ◽  
Mason Childs ◽  
Thien Duy Nguyen ◽  
Yassin Hassan
Keyword(s):  
Refractive Index ◽  
Uncertainty Quantification ◽  
Spacer Grid ◽  
Piv Measurements ◽  
Rod Bundle ◽  
Convergence Study

Convective heat transfer experiment of rod bundle flow with twist-vane spacer grid

2015 ◽  
Vol 295 ◽  
pp. 173-181 ◽  
Author(s):  
Wang Kee In ◽  
Chang Hwan Shin ◽  
Chi Young Lee
Keyword(s):  
Heat Transfer ◽  
Convective Heat Transfer ◽  
Convective Heat ◽  
Transfer Experiment ◽  
Spacer Grid ◽  
Rod Bundle
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