Yanhua Zheng - Concepedia

Author

Yanhua Zheng

Tsinghua University ORCID

Also Known As

Y. Zheng, Y.H. Zheng, Yan-hua Zheng, Yanhua ZHENG, Yanhua Zheng, Zheng Yan-Hua, Zheng Yanhua, Zheng, Yanhua

Publications

831

Citations

H-Index

Concepts

All Affiliations

Tsinghua University Key Laboratory of Nuclear Radiation and Nuclear Energy Technology RWTH Aachen University Nuclear Research and Consultancy Group Nuclear Materials Authority

About

Yanhua Zheng is an author at Tsinghua University specializing in engineering, heat transfer, and thermal engineering.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	17	22	641
2	Chemical Engineering	6	6	107
3	Civil Engineering	2	2	74
4	Electrical Engineering	2	2	78
5	Chemistry	1	1	14

Yanhua Zheng

Publications

677

Citations

H-Index

Page 1

	Year	Citations
Unconventional uranium in China's phosphate rock: Review and outlook Delei Shang, Michael Mew, Liliya Satalkina, Renewable and Sustainable Energy Reviews EngineeringNonmetallic Mineral DepositUnconventional UraniumGeologyMineral Deposit	2021	74
Thermohydraulic transient studies of the Chinese 200MWe HTR-PM for loss of forced cooling accidents Yanhua Zheng, Lei Shi, Yujie Dong Annals of Nuclear Energy EngineeringForced Cooling AccidentsMechanical EngineeringTemperature MeasurementChinese 200Mwe	2009	68
Water-ingress analysis for the 200 MWe pebble-bed modular high temperature gas-cooled reactor Yanhua Zheng, Lei Shi, Yan Wang Nuclear Engineering and Design EngineeringEnergy EfficiencyCivil EngineeringThermodynamicsWater-ingress Analysis	2010	55
Loss-of-cooling tests to verify inherent safety feature in the world’s first HTR-PM nuclear power plant Zuoyi Zhang, Yujie Dong, Fu Li, Joule ReliabilityElectrical EngineeringEngineeringNuclear ReactorsWorld ’ S	2024	52
Thermal hydraulic analysis of a pebble-bed modular high temperature gas-cooled reactor with ATTICA3D and THERMIX codes Yanhua Zheng, J. Lapins, Eckart Laurien, Nuclear Engineering and Design EngineeringThermix CodesThermal HydraulicsMechanical EngineeringThermal Management	2012	41
Study on the DLOFC and PLOFC accidents of the 200 MWe pebble-bed modular high temperature gas-cooled reactor with TINTE and SPECTRA codes Yanhua Zheng, M.M. Stempniewicz, Zhipeng Chen, Annals of Nuclear Energy EngineeringReactor SafetyPlofc AccidentsSpectra CodesNuclear Reactors	2018	39
Air ingress analysis of chimney effect in the 200 MWe pebble-bed modular high temperature gas-cooled reactor Zhipeng Chen, Yanhua Zheng, Jun Sun, Annals of Nuclear Energy EngineeringChimney EffectGas Turbine CombustionGas Turbine EngineThermodynamics	2017	32
Benchmark Calculation for the Steady-State Temperature Distribution of the HTR-10 under Full-Power Operation Fubing Chen, Yujie Dong, Yanhua Zheng, Journal of Nuclear Science and Technology EngineeringEnergy EfficiencyReactor DesignBenchmark CalculationReactor Physics	2009	26
On the Sustainability and Progress of Energy Neutral Mineral Processing Frederik Reitsma, Peter Woods, Martin Fairclough, Sustainability Fuel CycleEngineeringCritical MineralMineral ProcessingChemical Engineering	2018	25
CFD investigation of bypass flow in HTR-PM Ximing Sun, Zhipeng Chen, Jun Sun, Nuclear Engineering and Design EngineeringFluid MechanicsMechanical EngineeringComputational Fluid DynamicsTransport Phenomena	2017	23

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