Dissertation　

About 93 item dissertation in line with TL4,All kinds of nuclear reactors, nuclear power plant query results,the following is 1 to 50(Search took 0.054 seconds)

  1. Research on Virtual PWR Monitoring Systems,HuangZuo/Harbin Engineering University,0/2
  2. Numerical Simulation of Temperature Field and Thermal Stress of the Reactor Vessel in CEFR,LiChaoJun/Harbin Engineering University,0/34
  3. Multi-physical Processes Coupling Calculation Study for PWR,WangZuo/Harbin Engineering University,0/49
  4. A Study on Intelligent Control of PWR Power during the NPP's Load Following Operations,LiuJianXin/Harbin Engineering University,0/32
  5. Research on Simulation of Fast Reactor Core Physics Based on the Point Reactor Model,ZhuWenZhang/Harbin Engineering University,0/36
  6. Research on Simulation of Primary Coolant System of Sodium Cooled Fast Reactor,CuiManMan/Harbin Engineering University,0/55
  7. Design of Rdiation Shielding in the Advanced PWR,LiuJian/Harbin Engineering University,0/45
  8. Numerical and Experimental Study on Sodium Columnar Fire in Fast Reactor,ZhangPeng/Harbin Engineering University,0/93
  9. Studying of PRHRs in CEFR,SunXiaoLong/Harbin Engineering University,0/61
  10. Analysis of Coupled Dynamics on MSR under Accident Conditions,ZhaoLe/Nanjing University of Aeronautics and Astronautics,0/12
  11. Analysis on the Self-stabilization for a Molten Salt Reactor,SunNuan/Nanjing University of Aeronautics and Astronautics,0/18
  12. Modeling and Simulation of Helium Turbine Closed-cycle Device,Chen/Harbin Engineering University,0/16
  13. Application of the Passive Safety System to Fusion-fission Hybrid Reactor and Safety Analysis,YuZhangCheng/Tsinghua University,0/25
  14. A Study on Digital Control Technology of Pressurized Water Reactor Protection System,LiuZuo/Harbin Engineering University,0/23
  15. Numerical Simulation on the Hydraulic Characteristics of the Lower Chamber of the PWR,YangHongJian/Harbin Engineering University,0/38
  16. Burnup Measurement Study and Prototype Development in HTR-PM,ZuoWeiHua/Tsinghua University,0/22
  17. Exergy Analysis of Thermal Systerm for PWR Nuclear Power Plant,MaJun/Tohoku Electric Power University,0/11
  18. Internal cooling type PWR design and Study on the physical properties of core concept,ZengZhengKui/Nanhua University,0/8
  19. A Methodology for the Seismic Analysis of FBR Core Assemblies Using Variable Added Damping,ShangChaoZuo/North China Electric Power University,0/27
  20. Development of System Analysis Code with Three-dimensional Hot Pool Model for Pool-type Fast Breeder Reactor,SuiDanZuo/North China Electric Power University,0/26
  21. Numerical Simulation on Coolant Temperature Fluctuation from the Outlet of the Core in China Experimental Fast Reactor,LvJing/North China Electric Power University,0/61
  22. Numerical Study on External Reactor Vessel Natural Circulation Cooling for a Large-size Advanced PWR,JinZuo/Shanghai Jiaotong University,0/75
  23. The Separation and Storage of Tritium in Molten Salt Reactor Loop,HuangYu/Nanhua University,0/136
  24. Research on Physics Character of Fusion-fission Hybrid and PWR Combined Fuel Cycle System,MaXuBo/North China Electric Power University,0/159
  25. Neutronics Design and Study on Subcritical Spent Fuel Burner,WangMingHuang/University of Science and Technology of China,0/223
  26. Study on Void Fraction and Structure Optimization of Moderator Cell in Cold Neutron Source of China Advanced Research Reactor,LiXiaoMing/Xi'an Jiaotong University,0/62
  27. China Experimental Fast Reactor core single direction of the level of seismic analysis,WenJing/China Institute of Atomic Energy,1/125
  28. The Research and Development of the Digital Auto-startup & Power Regulating System of China Advanced Research Reactor,ZengHai/China Institute of Atomic Energy,3/535
  29. Research on Graphite Dust Behavior in 10MW High Temperature Gas-cooled Reactor,ZuoXiaoWei/Tsinghua University,2/444
  30. China Experimental Fast Reactor design phase of internal events a probabilistic safety assessment,YangHongYi/China Institute of Atomic Energy,5/606
  31. A Study on Core System of New Type Nuclear Powered Propulsion Installation,LiuTao/Harbin Engineering University,2/812
  32. The Development of Fault Diagnosis Systems of Sodium Pump for China Experiment Fast Reactor,FengJunZuo/China Institute of Atomic Energy,1/315
  33. MOX fuel module fast reactor transmutation research,ZhouPeiDe/China Institute of Atomic Energy,0/298
  34. Analysis of the fast reactor sodium fire,YuHong/China Institute of Atomic Energy,1/170
  35. Research on In-core Fuel Management and Optimization of Pressurized Water Reactor Nuclear Power Plants,ShiXiuAn/Tsinghua University,2/476
  36. Researches of Similitude Theory for Axial Flow Helium Compressor,ZhuRongKai/Harbin Engineering University,2/190
  37. Calculation and Application of Coarse Mesh Equivalent Homogenization Parameters with Non-Reflective Boundary Condition,HuangZuo/Shanghai Jiaotong University,0/94
  38. Research on 3D Simulation System for 10MW High Temperature Gas-cooled Reactor,MaChao/Tsinghua University,0/299
  39. Flow and Vibration Characteristic Research of Nuclear Main Pump under Station Blackout Accident,LiuXiaJie/Shanghai Jiaotong University,12/558
  40. Modification and Verification Assessment of Related Models in Licensing LOCA Analysis Program Platform Development,LuZuo/Shanghai Jiaotong University,2/114
  41. Visual simulation system development and research based on virtual instrument technology China Experimental Fast Reactor,WangXueFei/China Institute of Atomic Energy,0/102
  42. Helium-3 circuit design technology research,HuangXin/China Institute of Atomic Energy,0/29
  43. Study on the Tendency Forecast of Equipment Status Method for the Nuclear Power Plant,YuZhuJun/Harbin Engineering University,3/266
  44. China's nuclear power patent strategy research,WuXianFeng/China Institute of Atomic Energy,1/455
  45. The Simulation Study of the Neutron Guide for Neutron Scattering Project of China Advanced Research Reactor,LiangFeng/China Institute of Atomic Energy,0/37
  46. Sealing Analysis under Cooling and Heating Cycle for Reactor Pressure Vessel in Nuclear Power Station,HangHuaJiang/Chongqing University,0/264
  47. Research and Development of miniature neutron source reactor dual rod linkage microcomputer closed-loop control system,WangGuJun/China Institute of Atomic Energy,0/59
  48. Issued by the cold neutron source system thermal and cold neutron gain,ShenFeng/China Institute of Atomic Energy,3/68
  49. Study on Core Fuel Management of Slightly Enriched Uranium Fuel for CANDU6 Reactor,LiuZhongGuo/Shanghai Jiaotong University,0/102
  50. Study on the Improved Quasi-Static Nodal Green’s Function Method under Cylinder Goemetry,GaoZhenJia/Tsinghua University,2/110

Total 2 Pages First Previous 1 2 Next Last

© 2012 www.DissertationTopic.Net  Mobile