I.About us

TheDepartmentofNuclear Engineering and Technology(DNET),affiliatedwith the School of Energy & Power EngineeringinHuazhong University of Science andTechnology(HUST),originated fromtheDepartment of Engineering Physics initializedinHuazhong Institute of Technology back in 1958.In spite ofa sign of greatsuccess, the program wassuspendedin1962 due to the national situation.It was resumed by starting a jointstaff-trainingprogramwith China General Nuclear Power Group(CGN)in 2005 and thisjoint training program has lasted since then.In 2010,our department managed to make talent-training agreement with China National Nuclear Corporation(CNNC). More importantly,in the sameyear,theBachelor’s degree program of “Nuclear Engineering and Technology” wascertificated bythe Ministry of education of China.Now we have more than 100undergraduatestudentsand also a decent amount of graduate students.

Our departmentownsmany integrated platforms,such astheThermal-hydraulics ComprehensiveLaboratory,theAdvancedNuclearSystem Analysisand ComputationCenter, theNuclearPowerPlant Simulationand OperationCenter,andalso theNuclear-Environment-ChemicalInterdisciplinaryLaboratory.

Our departmentis incooperation withalot ofdomesticand abroad research institutes.We haveamutualprotocol with City University of HongKonginpostgraduate education.Wealsohave connectionswith many well-known universities like Purdue University and University of Wisconsin.

Nowthe department hasmore than 10teaching and research staffatprofessor, associate and assistant professorlevels.

II.Research Areas

Main research directions:

Design of advanced nuclear energy system and computer simulation.

Thermal-hydraulic and safety analysis of reactor.

Gas-liquid two-phase flow and heat transfer.

Heat transfer and flow inporous media.

Technologyof heat transfer enhancement in energy power plant.

Thermomechanical analysisin energy systems.

Radioactive waste processing.

Filtered containment venting system.

Nuclear material.

Plasma wall interaction in fusion reactors

Passive safety system.

Calculation in reactor physics and thermal hydraulic.

Main research contents:

Design and verification of passive safety system of GenerationIIInuclear plant.

Filtered containment venting system of nuclearpowerplant.

Computer simulation of the production and evolution of defects in materials under particle bombardment.

Computational method of reactor physics and thermal coupling.

Nuclear energy system’s thermal-hydraulic and safety analysis.

Scale modeling experiment and program verification of nuclear plant.

Containment’s leakage rate model and research about distributing rates.

Research about thermal conductive mechanism of SiC composite using in nuclear.

Research about removing radionuclide in water using carbon materials.

 

The teachers and their main research directions:

 

Yang Jun:yang_jun@hust.edu.cn, PhD of Purdue University

(I)ReactorThermal-hydraulic andsafety analysis.

(II)Gas-liquid two-phase flow and heat transfer.

(III)Design of passive safety system of GenerationIIInuclearreactor.

(IV)Experimental analysis ofCriticalHeatFluxin fuel buddle.

(V)Designand innovation of ContainmentFilteredVenting

Huang Xiaoming:xmhuang@hust.edu.cn, PhD of HUST

(I)Heat transfer and fluid flow in porous media.

(II)Gas-liquidtwophaseflow andheattransfer.

(III)Enhancementheattransfertechnologies inenergypowerequipment.

(IV)Thermodynamicsanalysis ofenergysystem.

(V)Heat andfluid flow indevices of NPP.

(VI)Theoreticalprediction of thesealingcharacteristics of the NPPcontainment.

XuLejin:xulejin@hust.edu.cn, PhD of Tsinghua University

(I)Treatment ofwater and wastewaterby chemical method.

(II) Treatment of low and mediumradioactive wasteusing advanced oxidation processes and cement solidification method.

(III)Treatment of radioactive wastewater by adsorption method.

(IV)Research about filtering method in filtered containment venting system.

Yang Zhangcan:yang_zhangcan@hust.edu.cn, PhD of Purdue University

(I)Multi-scale computer simulation in nuclear material.

(II)Low energy ion beam induced surface patterning.

(III)Ion-surface interactions

Deng Chengcheng:dengcc@hust.edu.cn, PhD of Tsinghua University

(I)Scalinganalysis on thermal-hydraulictest facilitiesof nuclear reactors.

(II)Best-estimate calculationsplusuncertaintyanalysisfor nuclear safety.

(III)Design and simulation of passive safety systems of advanced nuclear power plants.

(IV)Micro and nano-scale simulation ofthethermal propertiesof nuclear materials

Zhou Xiafeng:zhouxiafeng@hust.edu.cn, PhD of Tsinghua University

(I)Reactor physicsnumerical methods.

(II)Reactorthermal-hydraulics numerical methods.

(III)Simulation of nuclear complex coupling system.

(IV)Research about filtered containment venting system.

(V)Solving large sparse linear systems.