X.X. Li - Concepedia

Author

X.X. Li

Chinese Academy of Sciences ORCID

Also Known As

Li, Xiaoxiao, X. X. Li, X.X. Li, Xiao-Xiao Li, XiaoXiao Li, Xiaoxiao Li, Xuankang Li

Publications

763

Citations

H-Index

Concepts

All Affiliations

Chinese Academy of Sciences Shanghai Institute of Applied Physics University of Chinese Academy of Sciences Key Laboratory of Nuclear Radiation and Nuclear Energy Technology Yunnan University

About

X.X. Li is an author at Chinese Academy of Sciences specializing in engineering, materials science, and nuclear energy.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	13	17	524
2	Applied Physics	4	4	123
3	Chemistry	3	3	75
4	Chemical Engineering	2	2	74
5	Computer Engineering	1	1	17

X.X. Li

Publications

703

Citations

H-Index

Page 1

	Year	Citations
Quantitative optimization of interoperability during feature-based data exchange D.J. Zhang, Fazhi He, Soonhung Han, Integrated Computer-Aided Engineering	2015	102
Catalytic synthesis and photoluminescence of needle-shaped 3C–SiC nanowires Tianqi Jia, X.X. Li, Z. Xu, Solid State Communications Materials ScienceEngineeringNanomaterialsNanotechnologyNeedle-shaped 3C–sic	2003	72
Optimization of temperature coefficient and breeding ratio for a graphite-moderated molten salt reactor Chunyan Zou, X. Z. Cai, Dazhen Jiang, Nuclear Engineering and Design Materials ScienceChemical EngineeringEngineeringThermal HydraulicsEnergy Efficiency	2014	64
Analysis of minor actinides transmutation for a Molten Salt Fast Reactor Chenggang Yu, X.X. Li, X. Z. Cai, Annals of Nuclear Energy Materials ScienceEngineeringThermodynamicsChemistryMinor Actinides Transmutation	2015	52
Minor actinide incineration and Th-U breeding in a small FLiNaK Molten Salt Fast Reactor Chenggang Yu, X.X. Li, X. Z. Cai, Annals of Nuclear Energy Chemical KineticsEngineeringTh-u BreedingMinor Actinide IncinerationNuclear Reactors	2016	50
Possible scenarios for the transition to thorium fuel cycle in molten salt reactor by using enriched uranium Deyang Cui, X.X. Li, Shaopeng Xia, Progress in Nuclear Energy Fuel CycleNuclear Fuel BurnupNuclear Waste ManagementEngineeringNuclear Fuel	2017	45
Analysis of thorium and uranium based nuclear fuel options in Fluoride salt-cooled High-temperature Reactor X.X. Li, X. Z. Cai, Dazhen Jiang, Progress in Nuclear Energy Nuclear Waste ManagementNuclear PhysicsEngineeringNuclear FuelNuclear Reactor Engineering	2014	37
Transition toward thorium fuel cycle in a molten salt reactor by using plutonium Deyang Cui, Shaopeng Xia, X.X. Li, Nuclear Science and Techniques Fuel CycleNuclear Fuel BurnupEngineeringNuclear FuelNuclear Reactor Engineering	2017	34
Preconceptual nuclear design of a 50 kWth heat pipe cooled micro molten salt reactor (micro-MSR) Deyang Cui, Ye Dai, X. Z. Cai, Progress in Nuclear Energy Advanced Nuclear ReactorsEngineeringKwth Heat PipeReactor DesignMechanical Engineering	2021	30
Highlights from the ARGO-YBJ experiment G. Aielli, C. Bacci, B. Bartoli, Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment Argo-ybj ExperimentPhysicsNeutrino Astronomy	2010	25

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