Qi Zhang , Zhenhai Liu , Yile Zhang , Hua Pang , Mengke Cai , Zhenhan Hong , Guangliang Yang , Haoyu Wang , Li Liu , Yao Xiao , Hanyang Gu
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引用次数: 0
Abstract
The helical cruciform fuel (HCF) is characterized as self-mixing and self-supporting, which has promising applications in advanced nuclear power devices. In the presented work, the transverse mixing behaviors of the 4 × 4 HCF assembly with the Reynolds number scope of 5.90 × 102 to 1.13 × 104 were investigated by mixing experiment and sub-channel analysis. The wire-mesh sensor (WMS) device for the complex-structured rod bundle channel was designed, which was utilized for the concentration measurement in the range of 0.01352 mol/L to 0.02916 mol/L. The one-way mixing at rod gap type Ⅰ and two-way mixing at rod gap type ⅠⅠ were revealed by the evolution of sub-channel concentration profile along the axial height of HCF assembly. The mixing coefficient of the HCF assembly was found to be a geometry depended constant, which was 0.022 for the 4 × 4 HCF assembly. It is confirmed that the transverse mixing of HCF assembly is dominant by flow sweeping effect rather than the turbulent mixing. The flow sweeping mixing model for the HCF assembly was developed, which involves two sets of momentum equations. In general, the presented work provides the fundamental experimental data and applicable mixing model for the development of sub-channel code for HCF assembly.
期刊介绍:
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.
NET covers all fields for peaceful utilization of nuclear energy and radiation as follows:
1) Reactor Physics
2) Thermal Hydraulics
3) Nuclear Safety
4) Nuclear I&C
5) Nuclear Physics, Fusion, and Laser Technology
6) Nuclear Fuel Cycle and Radioactive Waste Management
7) Nuclear Fuel and Reactor Materials
8) Radiation Application
9) Radiation Protection
10) Nuclear Structural Analysis and Plant Management & Maintenance
11) Nuclear Policy, Economics, and Human Resource Development