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Institute Of Nuclear Energy Technology Tsinghua University | 論文
- Step Dynamic Process of the Hydrauliocally-driven Control Rod, (II) Theoretical Model on Step-down Process
- Gas Space and Flow Stability in Integrated Reactors
- Solvothermal Synthesis of γ-LiV_2O_5 Nanorods as Cathode Material for Rechargeable Lithium Batteries
- Optimization of Hot Gas Chamber in High Temperature Reactor
- Numerical Analysis of the Lifting Beam's Influence on Flow Fields in Planar Fuel Assemblies
- Experimental Study of the Pressure Discharge Process for the Hydraulic Control Rod Drive System Stepped Cylinder
- Experimental and Operational Verification of the HTR-10 Once-Through Steam Generator (SG) : Heat-transfer and Hydrodynamic Features of the Once-Through Steam Generator
- Experiment and Verification Test of the Once-through Steam Generator of the 10MW High-temperature Gas-cooled Reactor Flow Stability of the Once-through Steam Generator
- NMR Spectroscopic Studies on Complex Formation between Dimeric (R)-3-Hydroxybutanoic Acid and β-Cyclodextrin
- Conformational Analysis of Oligomers of (R)-3-Hydroxybutanoic Acid in Solutions by ^1H NMR Spectroscopy
- Conformational Behavior of Methyl (3R)-3-{[{3'R)-3'-Hydroxybutanoyl]oxy}butanoate in Solutions: Effect of Intramolecular Hydrogen Bond
- Complex Formation between Poly(methyl vinyl ether) and γ-Cyclodextrin
- ICONE11-36622 PRELIMINARY DESIGN OF THE POWER CONVERSION UNIT WITH DIRECT GAS-TURBINE CYCLE FOR THE HTR-10
- ICONE11-36524 PRELIMINARY MODAL ANALYSIS AND STRUCTURE DESIGN OF AN HTR-10 PCU ROTOR WITH AN ACTIVE MAGNETIC BEARING
- Thermalhydraulic Investigation Using a Test Facility Simulating 200 MW Integral Heating Reactor
- A Monte Carlo Model for Gamma-Ray Klein-Nishina Scattering Probabilities to Finite Detectors
- Review of Thermalhydraulic Experimental Researches at INET
- On-line solid-phase extraction of ceramides from yeast with ceramide III imprinted monolith
- Numerical Investigation on Flow Excursion Boundary of a Full Power Natural Circulation Reactor
- Two New Type Passive Residual Heat Removal Systems for Nuclear Reactors