tailieunhanh - Research on the structure design of the LBE reactor coolant pump in the lead base heap

This study mainly focuses on the structural design optimization of the 4th-generation reactor coolant pump, including analysis of external characteristics, inner flow, and transient characteristic. It was found that: the reactor coolant pump with a central symmetrical dual-outlet volute structure has better radialdirection balance, the pump without guide vane has better hydraulic performance, and the pump with guide vanes has worse torsional vibration and pressure pulsation. | Research on the structure design of the LBE reactor coolant pump in the lead base heap Nuclear Engineering and Technology 51 (2019) 546e555 Contents lists available at ScienceDirect Nuclear Engineering and Technology journal homepage: Original Article Research on the structure design of the LBE reactor coolant pump in the lead base heap Yonggang Lu a, Rongsheng Zhu a, *, Qiang Fu a, Xiuli Wang a, b, Ce An a, Jing Chen a, c a National Research Center of Pumps, Jiangsu University, Zhenjiang, 212013, Jiangsu, China b Key Laboratory of Fluid and Power Machinery of Ministry of Education, Xihua University, Chengdu 610039, Sichuan, China c College of Mechanical & Power Power Engineering of China Three Gorges University, Yichang, 443002, China a r t i c l e i n f o a b s t r a c t Article history: Since the first nuclear reactor first critical, nuclear systems has gone through four generations of history, Received 31 March 2018 and the fourth generation nuclear system will be truly realized in the near future. The notions of SVBR Received in revised form and lead-bismuth eutectic alloy coolant put forward by Russia were well received by the international 3 September 2018 nuclear science community. Lead-bismuth eutectic alloy with the ability of the better neutron economy, Accepted 28 September 2018 Available online 3 October 2018 the low melting point, the high boiling point, the chemical inertness to water and air and other features, which was considered the most promising coolant for the 4th generation nuclear reactors. This study mainly focuses on the structural design optimization of the 4th-generation reactor coolant pump, Keywords: LBE including analysis of external characteristics, inner flow, and transient characteristic. It was found that: Reactor coolant pump the reactor coolant pump with a central symmetrical dual-outlet volute structure has better radial- SVBR direction

• Năng lượng
• Nuclear engineering and technology
• Research on the structure design
• The LBE reactor coolant pump in the lead base heap
• LBE reactor coolant pump
• Central symmetrical dual outlet volute structure
• Better radialdirection balance
• Integral nuclear data validation
• Experimental spent nuclear fuel compositions
• Economic Co operation and Development
• Nuclear Energy Agency
• Nuclear Criticality Safety
• Expanded spent fuel isotopic compositions
• Nuclear reactor vessel water level prediction during severe accidents
• Deep neural networks
• Nuclear power plants
• Maintain nuclear reactor integrity
• Special issue on the International Symposium
• Future Instrumentation and Control for Nuclear Power Plants
• The Nuclear Engineering and Technolog
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• Application to fault diagnosis of nuclear plants
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• Nuclear Heating Reactor
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• Radioactive effluents released from Korean nuclear power plants
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• Korean nuclear power plants
• Nuclear power plant
• The recycling of nuclear graphite after micro oxidation
• Nuclear graphite after micro oxidation
• Whether ground micro oxidation graphite
• The oxidized graphite particles
• The recycling of nuclear graphite
• Statistical model for forecasting uranium prices
• Estimate the nuclear fuel cycle cost
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• The statistical autoregressive integrated moving average
• Distinct properties of tungsten austenitic stainless alloy
• Potential nuclear engineering material
• Interchanging the molybdenum in standard SS316 by tungsten
• Gamma and neutron shielding Interchanging the molybdenum
• Nuclear engineering and design
• Brayton cycle
• Supercritical carbon dioxide
• Nuclear engineering
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• Control strategy
• Seismic fragility evaluation
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• Seismic fragility analysis
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• Safety system in nuclear power plant
• Embedded Real Time Safety Systems
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• Nuclear power plant medium voltage switchgear
• High energy arcing fault
• Ultra high performance fiber reinforced concrete nuclear waste container
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• The dry storage container
• Canadian Nuclear facilities
• Real time estimation of break sizes during LOCA
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• Loss of coolant accidents
• Nordic research and development cooperation
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• Nordic Nuclear Safety Research
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• Nuclear Shield Building
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• Debris Filtering Performance
• Debris Induced Failure
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• Multivariable decision making process
• The nuclear power plant
• Development of an information reference system
• Reconstruction models of nuclear power plants
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• Six nuclear power plant workers
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