11 results on '"Zhang, Kanglong"'
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2. KIT Multi-scale thermal–hydraulic coupling methods for improved simulation of nuclear power plants
3. Cost-effective recycling of spent LiMn2O4 cathode via a chemical lithiation strategy
4. Validation of the TWOPORFLOW code for the core analysis of liquid metal-cooled reactor with selected experiments
5. Development of the coupled code – TRACE/TrioCFD based on ICoCo for simulation of nuclear power systems and its validation against the VVER-1000 coolant-mixing benchmark
6. Optimization and verification of the coupled code TRACE/SubChanFlow using the VVER-1000 coolant mixing benchmark data
7. Optimum design of shim rod assembly absorber bundle for Lead Bismuth Eutectic (LBE) cooled reactor.
8. Development and verification of the coupled thermal–hydraulic code – TRACE/SCF based on the ICoCo interface and the SALOME platform.
9. Multi-scale coupling of CFD code and sub-channel code based on a generic coupling architecture.
10. The Dynamic-Implicit-Additional-Source (DIAS) method for multi-scale coupling of thermal-hydraulic codes to enhance the prediction of mass and heat transfer in the nuclear reactor pressure VESSEL.
11. On-chip coupled-resonator filter with controllable transmission zeros based on hybrid coupling technique.
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