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- · 双孔对直接接触冷凝特性影响的实验研究.原子能科学技术.2021
- · Research on backflow characteristics in U-tube of forced circulation steam generator under ocean conditions.Progress in Nuclear Energy.2021
- · Numerical analysis on heat transfer enhancement of sCO2 in the tube with twisted tape.Nuclear Engineering and Design.2022
- · Porosity effect on the thermal and mechanical properties of U-50Zr alloy: A molecular dynamics study.Journal of Nuclear Materials.2023
- · Numerical study on the effects of guide thimble on critical heat flux in a 5 x 5 fuel assembly.ANNALS OF NUCLEAR ENERGY.2022
- · Experimental Study on Dryout and Post-Dryout Heat Transfer in a Three-Rod Bundle With Spacer Grids.29th International Conference on Nuclear Engineering.2022
- · Numerical study on the boiling heat transfer and critical heat flux in a simplified fuel assembly with 2x2 helical cruciform rods.PROGRESS IN NUCLEAR ENERGY.2022
- · Numerical investigation on the performance of gas-lift pump with large density ratio of liquid to gas.INTERNATIONAL JOURNAL OF MULTIPHASE FLOW.2022
- · Prediction of thermohydraulics in shell side of CAP1400 steam generator by two-fluid porous media model.PROGRESS IN NUCLEAR ENERGY.2022
- · Comparison on the thermal-hydraulic characteristics of wire-wrapped fuel and helical cruciform fuel by numerical simulation.ANNALS OF NUCLEAR ENERGY.2022
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