Experimental investigation on split-mixing-vane forced mixing in pressurized water reactor fuel assembly

Xiong, Juntao; Qu, Wenhai; Zhang, Tengfei; Chai, Xiaoyan; Liu, Xiaojing; Yang, Yanhua

doi:10.1016/j.anucene.2020.107450

Cited by 39 publications

(4 citation statements)

References 34 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The lateral pressure loss changes with the orienting angle based on a series of CFD simulations (Li and Gao, 2014;Chang and Tavoularis, 2015;Sibel Tas-Koehler et al, 2020). The lateral pressure loss changes with the distance from the split-type mixing vane spacer grid, and the cross flow develops from two vortices to a single vortex, and then it decays gradually (McClusky et al, 2002;McClusky et al, 2003;Chang et al, 2008;Qu et al, 2019a;Qu et al, 2019b;Xiong et al, 2020). However, lateral pressure measurements were reported in a few studies (Qu et al, 2019a;Turankok et al, 2020;Xiong et al, 2020).…”

Section: Lateral Pressure Lossmentioning

confidence: 99%

“…In the MATiS-H benchmark exercise (Agbodemegbe et al, 2015;Chang and Tavoularis, 2015), the pressure distribution on the surface of mixing vanes was the mechanism of the cross-flow pattern, and the cross-flow resistance was investigated using the CFD simulation. In the studies by Qu et al (2019a) and Xiong et al (2020), a new sliding pressure loss measurement system was designed to measure the lateral pressure loss between sub-channels. The lateral pressure loss decays as an exponential function of the distance from the spacer grid, and the cross-flow resistance was fitted into a correlation of distance from the spacer grid.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Experimental Study of Pressure Loss in a 5 × 5–Rod Bundle With the Mixing Vane Spacer Grid

Yao

Xiong

et al. 2021

Front. Energy Res.

Self Cite

View full text Add to dashboard Cite

Axial and lateral pressure loss in a 5 × 5 rod–bundle with a split-type mixing vane spacer grid was experimentally measured using differential pressure transmitters at different sub-channel Reynolds numbers (Re) and orienting angles. The geometrical parameters of the 5 × 5–rod bundle are as follows: they have the same diameter (D = 9.5 mm) and pitch (p = 12.6 mm) as those of real fuel rods of a typical pressurized water reactor (PWR), with a sub-channel hydraulic diameter (Dh) of 11.78 mm. The characteristics and resistance models of pressure loss are discussed. The main axial pressure loss is caused by the spacer grid, and the spacer grid generates additional wall friction pressure loss downstream of the spacer grid. The lateral pressure loss shows strong correlations with orienting angles and distance from the spacer grid. The lateral pressure loss shows a sudden burst in the mixing vanes region and a slight augmentation at z = 3Dh. After 3Dh, the lateral pressure loss decays in an exponential way with distance from the spacer grid, and it becomes constant quickly at z = 20Dh.

show abstract

Section: Lateral Pressure Lossmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Experimental Study of Pressure Loss in a 5 × 5–Rod Bundle With the Mixing Vane Spacer Grid

Yao

Xiong

et al. 2021

Front. Energy Res.

Self Cite

View full text Add to dashboard Cite

show abstract

“…Nguyen and Hassan (2017) and Matozinhos et al (2021) studied the turbulent length scales in the axial velocity field in a 5 × 5 rod bundle using a spacer grid. Qu et al (2019a), Qu et al (2019b), Qu et al (2019c), Qu et al (2021), Xiong et al (2020b), and Qu et al (2023) applied PIV to obtain the lateral flow in a 5 × 5 rod bundle using a spacer grid, and they investigated subchannel mixing models based on the experimental data.…”

Section: Introductionmentioning

confidence: 99%

Large eddy simulation of a turbulent flow in a 5 x 5 rod bundle with a mixing vane spacer grid

Lu,

2024

Front. Energy Res.

View full text Add to dashboard Cite

In fuel assemblies of pressurized water reactors (PWRs), mixing-vane spacer grids are extensively employed to array fuel rods and enhance inter- and intra-subchannel mixing. The turbulent flow downstream of spacer grids is essential knowledge to support the design of spacer grids and mixing vanes. As a high-fidelity approach for turbulence simulation, large eddy simulation (LES) results are assessed with the high-resolution flow field measured with particle image velocimetry (PIV). The LES results reveal a mixing vane effect on vortex structures and Reynolds stresses. The mechanism of vortex generation at the mixing vanes and the development downstream of the spacer grid are visualized by the Q-criterion. The distributions of the root mean square fluctuating velocity and Reynolds stresses decay rapidly downstream of the spacer grid. The secondary flow intensity downstream of the spacer grid predicted by LES is evaluated and follows an exponentially decaying law with distance from the spacer grid.

show abstract

“…Under accident conditions, there are several kinds of flow regimes existing in the rod bundle channel. Moreover, due to the interchannel mixing mechanisms (Xiong et al, 2020) and the cross flow caused by the mixing vanes between adjacent open channels (Qu et al, 2019), the flow regime could transition from annular flow to bubble flow or slug flow. Accordingly, the corresponding CHF will also transition from the DO to DNB regime (Yang et al, 2019), as shown in Figure 1.…”

Section: Introductionmentioning

confidence: 99%

Investigation on Rod Bundle CHF Mechanistic Model for DNB and DO Prediction Under Wide Parameter Range

et al. 2021

View full text Add to dashboard Cite

For a water cooled reactor, the key thermal-hydraulic parameters span a wide range corresponding to different CHF regimes. Under accident conditions, due to the flow regime transition and interchannel mixing effect, the corresponding CHF can transition from the DO to DNB regime. In order to continuously and accurately predict DNB and DO regime CHF under wide parameter range for rod bundle channel, a comprehensive CHF mechanistic model covering the DNB and DO regime CHF prediction is established based on the rod bundle CHF-regime criterion. The DNB regime CHF mechanistic model of superheated liquid layer depletion under turbulence fluctuation bubbles and the mature DO regime CHF mechanistic model are combined to form the comprehensive CHF model. Furthermore, the comprehensive CHF model is assessed by 5 × 5 rod bundle CHF experimental data independently obtained by the Nuclear Power Institute of China (NPIC). The statistical evaluation and parametric trend analysis show that the maximum mean error of P/M is within ±22%, and the local pressure, mass flux, and quality do not have any effects on the average deviations of the predicted flux P from the measured flux M. This indicates that the comprehensive CHF mechanistic model can accurately and continuously predict the DNB and DO regime CHF in the rod bundle channel.

show abstract

Experimental investigation on split-mixing-vane forced mixing in pressurized water reactor fuel assembly

Cited by 39 publications

References 34 publications

Experimental Study of Pressure Loss in a 5 × 5–Rod Bundle With the Mixing Vane Spacer Grid

Experimental Study of Pressure Loss in a 5 × 5–Rod Bundle With the Mixing Vane Spacer Grid

Large eddy simulation of a turbulent flow in a 5 x 5 rod bundle with a mixing vane spacer grid

Investigation on Rod Bundle CHF Mechanistic Model for DNB and DO Prediction Under Wide Parameter Range

Contact Info

Product

Resources

About