As a strong support for achieving the low-carbon goal, nuclear power generation plays an increasingly important role. The nuclear safety has always been the focus of the international community. The steam generator is the key connection component between the primary and secondary circuit in nuclear power plants. In recent years, the Once-Through Steam Generator (OTSG) has been widely used in small modular reactors and lead-bismuth cooled fast reactors. However, its flow and heat transfer characteristics are significantly different from conventional inverted U-tube steam generators.
During the operation of OTSG, there is a two-phase flow phase change process from single-phase water to superheated steam in the secondary side of the working medium. The heat and water storage capacity of the secondary side are very small, leading to the quick respond of operating parameters. Especially during start-up and shutdown, there are strong flow instability and wall temperature fluctuation in OTSG, which easily leads to continuous flow oscillation, as well as flow-induced vibration and large stress of tube sheet structure. In order to solve these problems, it is necessary to focus on the works on the thermal and hydraulic behaviors in OTSG.
The themes of Research Topic include the following, but are not limited to:
• Two-phase heat transfer resistance relationship;
• Evaporation point liquid film development model;
• Flow instability analysis;
• Start-up, shutdown, partial loop, low power and other operation modes;
• Pressure control;
• Flow induced vibration;
• Tube sheet expansion joint and fatigue analysis;
• Impact analysis and other research work.
As a strong support for achieving the low-carbon goal, nuclear power generation plays an increasingly important role. The nuclear safety has always been the focus of the international community. The steam generator is the key connection component between the primary and secondary circuit in nuclear power plants. In recent years, the Once-Through Steam Generator (OTSG) has been widely used in small modular reactors and lead-bismuth cooled fast reactors. However, its flow and heat transfer characteristics are significantly different from conventional inverted U-tube steam generators.
During the operation of OTSG, there is a two-phase flow phase change process from single-phase water to superheated steam in the secondary side of the working medium. The heat and water storage capacity of the secondary side are very small, leading to the quick respond of operating parameters. Especially during start-up and shutdown, there are strong flow instability and wall temperature fluctuation in OTSG, which easily leads to continuous flow oscillation, as well as flow-induced vibration and large stress of tube sheet structure. In order to solve these problems, it is necessary to focus on the works on the thermal and hydraulic behaviors in OTSG.
The themes of Research Topic include the following, but are not limited to:
• Two-phase heat transfer resistance relationship;
• Evaporation point liquid film development model;
• Flow instability analysis;
• Start-up, shutdown, partial loop, low power and other operation modes;
• Pressure control;
• Flow induced vibration;
• Tube sheet expansion joint and fatigue analysis;
• Impact analysis and other research work.
