Yongan Ji , Qiunan Sun , Yifei Ren , Ming Ding , Zehua Guo , Zhongning Sun
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引用次数: 0
Abstract
The Passive Containment Cooling System (PCCS) is one of the passive safety systems in HPR1000. Its maximum continuous operating time depends entirely on the running time of the external containment water tank. Hence, removing the heat from the tank and prolonging the water tank’s operating time are undoubtedly the keys to the problem. In this study, adding air cooling channels on the outside of the water tank has been modeled using numerical simulations to investigate the characteristics of a passive mechanism of shutdown heat removal. A basic channel is selected to verify the feasibility of prolonging the PCCS maximum continuous operating time and explore the air cooling channel’s maximum capacity to remove heat from core decay from three aspects: the emissivity of the surface materials, channel spacing, and chimney height. Due to the uncertainty of the turbulence model and the geometry simplification, ten independent reliable calculations under identical conditions demonstrate that an optimal air cooling channel geometry design could prolong the maximum continuous operating time of the PCCS up to the order of 116–120 h, which is substantially higher than 72 h of the reference case. Furthermore, the selection of surface materials with a high emissivity and increasing chimney height would be crucial measures in safety design. This study provides future researchers with a guideline for designing passive safety measures for advanced reactors.
期刊介绍:
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.