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Featured researches published by Weiqian Zhuo.


Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications | 2013

Helium Permeability Measurement of SiC Ceramic Composites for Advanced Reactor Application

Weiqian Zhuo; Fenglei Niu; Yungan Zhao; Houbo Qi; Zulong Hao; Pengfei Hao

Permeability of helium gas of Silicon carbide ceramic composites material, which is one of the most important properties in application of SiC composite for advanced reactors, is studied by using a simple, low-cost test system. The test system can not only qualitatively determine whether the sample is permeable or not, but also quantitatively measure the permeability for the permeable ones by water displacement. The tests are conducted with low pressure in room temperature. The permeability of the SiSiC composite depends on the preparation method. In four flat-plate materials prepared by different processes for the test, the splint based SiSiC and cordierite coated fiber reinforced SiSiC are hermetic, the permeability of uncoated fiber reinforced SiSiC and CVD carbon coated fiber reinforced SiSiC are 0.216cm2/s and 0.109cm2/s, which imply that the permeability is cut in half with the coating. The samples are scanned under SEM to analyze their microscopic structures and verified that the difference of permeability is related to their coatings as well as the pores and cracks.Copyright


Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications | 2013

Young’s Modulus and Gas Tightness Measurement of Ceramic Matrix Composite-SiC for Advanced Reactor Application

Yungan Zhao; Fenglei Niu; Yu Yu; Weiqian Zhuo; Zulong Hao; Wei Xiao

Considering the core outlet temperature of high temperature gas-cooled reactor (HTGR) is above 1000 °C and in the accident conditions, a new type of heat-resistant silicon carbide (SiC) ceramic matrix composites needs to be developed. Analysis of the Young’s modulus and gas tightness of ceramic matrix composite-SiC should be paid attention to due to the inherent brittleness and large porosity of SiC ceramics and also the high temperature and high pressure environment where the fuel cladding works. In this paper, a set of measuring device is designed, which is capable of measuring both Young’s modulus and gas tightness of sic ceramic materials. In order to avoid the shatter of ceramic matrix composite-SiC due to excessive deformation in the measurement process of Young’s modulus, Wheatstone bridge principle is used in the experiment to convert the changes of resistance which generated by the micro-deformation of resistance strain gage adhesive on the surface of the specimen into voltage signal, then the relationship between the amplified voltage signal and the strain of specimen can be established, thereby the Young’s modulus of the specimen can be calculated. The measuring method used in this experiment is more rapid, accurate and economic than previous methods. Besides, there is no need for extra measuring device to measure gas tightness of specimen for it has been taken into account in designing process.Copyright


Nuclear Engineering and Design | 2016

The studies of mixing and thermal stratification in SMR containments

Fenglei Niu; Weiqian Zhuo; Junchi Cai; Xiaowei Su; Yingqiu Hu; Yungan Zhao; Tengfei Ma; Yeyun Wang; Yu Yu


Nuclear Science and Techniques | 2016

Influence of injection temperature and flow rate on mixing and stratification in small passively cooling enclosures

Weiqian Zhuo; Fenglei Niu; Junchi Cai; Xiaowei Su; Yingqiu Hu; Yungan Zhao; Yu Yu


Nuclear Engineering and Design | 2018

Experimental and CFD analysis of the effects of debris deposition across the fuel assemblies

Muhammad Safeer Azam; Fenglei Niu; Da Wang; Weiqian Zhuo


Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues | 2017

Numerical Simulations of Two-Phase Flow in a Fuel Assembly of Blockage due to LOCA

Jingwen Ren; Fenglei Niu; Weiqian Zhuo; Da Wang


Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management | 2017

Experimental Study of Debris-Loading Head Loss Test for PWR Fuel Assembly After LOCA

Da Wang; Fenglei Niu; Weiqian Zhuo; Jingwen Ren; Zhangpeng Guo; Hammad Aslam Bhatti


Annals of Nuclear Energy | 2017

Experimental analysis of steam mixing and thermal stratification phenomena related to small steel containment studies

Shengfei Wang; Yeyun Wang; Weiqian Zhuo; Fenglei Niu; Yu Yu; Zhangpeng Guo; Yaou Shen; Wei Chen; Xiaowei Jiang


Annals of Nuclear Energy | 2017

Modeling and experimental studies on air buoyant jets for application to small containments

Tengfei Ma; Fenglei Niu; Weiqian Zhuo; Yeyun Wang; Taskeen Warraich; Safeer Azam


Annals of Nuclear Energy | 2017

Hermeticity and tensile experiment of small plate-type SiC ceramic composites for advanced reactor applications

Weiqian Zhuo; Fenglei Niu; Yungan Zhao; Jun Liu

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Fenglei Niu

North China Electric Power University

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Yungan Zhao

North China Electric Power University

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Da Wang

North China Electric Power University

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Yu Yu

North China Electric Power University

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Yeyun Wang

North China Electric Power University

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Zhangpeng Guo

North China Electric Power University

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Hammad Aslam Bhatti

North China Electric Power University

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Jingwen Ren

North China Electric Power University

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Junchi Cai

North China Electric Power University

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Tengfei Ma

North China Electric Power University

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