スポンサーリンク
Institute of Nuclear Energy technology, Tsinghua University | 論文
- Hydraulic Performance of Small Bending Radius Helical Coil-Pipe
- Research Method and Two-Phase Flow Stability of the Steam Generator of HTR-10
- Step Dynamic Process of the Hydraulically-driven Cnrtrol Rod, (I) Experiment of Dynamic Process Behavior
- Temperature Measuring System of the In-core Components for Chinese 10MW High Temperature Gas-cooled Reactor
- Preparation of UO_2 Kernel for HTR-10 Fuel Element
- ICONE11-36521 FEASIBILITY STUDY ON DIFFERENT GAS TURBINE CYCLES FOR HIGH TEMPERATURE GAS-COOLED REACTOR
- Primary System Aerodynamic Characteristics and Associated Circulator Operational Performance of HTR-10
- Two New Type Passive Residual Heat Removal Systems for Nuclear Reactors
- Primary System Aerodynamic Characteristics and Associated Circulator Operational Performance of HTR-10