Gonghao Lu , Guangxu Zhang , Chao Jin , Jiajun Tang , Rongshun Xie , Gang Hong , Yaoli Zhang
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引用次数: 0
Abstract
To investigate the passive residual heat removal capacity of supercritical carbon dioxide (S-CO2), this study takes a 12MWe lead–bismuth fast reactor as an example and analyzes two indirect S-CO2 passive residual heat removal system (PRHRS) designs (design 1 based on steam generator (SG) and design 2 based on independent heat exchanger (IHEX)). One-dimensional modeling was conducted using the Modelica language, and detailed analysis was performed on important components. The passive residual heat removal capacity of S-CO2 was evaluated through simulation calculations. The research results show that the maximum temperature of relevant design based on SG and IHEX does not exceed the pipeline design basis. Both design can reasonably and effectively remove the residual heat from the reactor core. The original equipment of the S-CO2 Brayton recompression cycle can be directly used to remove residual heat without compromising the relatively simple arrangement. The reasons for the occurrence of peak flow rate are discussed. Meanwhile, an analysis of the outlet temperature of the loop under different pressures in the SG design concludes that the operating pressure of the scheme should exceed 8.5 MPa.
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.