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Institute of Nuclear Energy technology, Tsinghua University | 論文
- ICONE11-36512 RESEARCHING ON KNOWLEDGE ARCHITECTURE OF DESIGN BY ANALYSIS BASED ON ASEME CODE
- ICONE11-36511 AN OBJECT-ORIENTED HYBRID KNOWLEDGE REPRESENTATION METHOD BASED ON THE ASME CODE
- Hydrogen-Defect Shallow Donors in Si
- Performance Analysis of Gamma-Ray-Irradiated Color Complementary Metal Oxide Semiconductor Digital Image Sensors
- Degradation of Black and White Complementary Metal Oxide Semiconductor (CMOS) Digital Image Sensor by Gamma-Irradiation : Semiconductors
- Annealing Behavior of Defects in Neutron-Transmutation-Doped Floating Zone Si
- Seismic Analysis of Hydraulic Control Rod Driving System
- Experiment Study on Rod Ejection Accident Hydraulic Control Rod Driving System
- Step Dynamic Process of the Hydrauliocally-driven Control Rod, (II) Theoretical Model on Step-down Process
- 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
- 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
- Review of Thermalhydraulic Experimental Researches at INET
- Numerical Investigation on Flow Excursion Boundary of a Full Power Natural Circulation Reactor
- Two New Type Passive Residual Heat Removal Systems for Nuclear Reactors