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Once-through steam generators (OTSGs) are critical components in advanced nuclear power systems, including integrated fast reactors (IFR), high-temperature gas-cooled reactors (HTR), and integrated pressurized water reactors (IPWR). These systems face dynamic operational challenges due to load-following requirements and rapid start-up/shutdown cycles. Compared to natural circulation steam generators, OTSGs exhibit lower thermal inertia and material content, leading to heightened sensitivity to thermodynamic fluctuations. This study proposes a novel sliding boundary lumped parameter model for OTSG operational control, derived from mass, momentum, and energy conservation principles. The model simplifies existing frameworks by reducing the number of governing differential equations from 11 to 4 while preserving accuracy. Numerical validation using a NuScale-type IPWR demonstrates that the model captures key thermohydraulic behaviors, including superheated section dynamics and open-loop responses under transient conditions. This work provides a foundation for real-time control system design and fault detection in SMR applications.

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Dynamic Modeling of Once Through Steam Generators for Operational Control

  • 会议论文

  • 发表日期：

    2026年

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  • Bowen Li,
  • Henglong Lin,
  • Zeguang Li,
  • Huifu Wang

摘要

Once-through steam generators (OTSGs) are critical components in advanced nuclear power systems, including integrated fast reactors (IFR), high-temperature gas-cooled reactors (HTR), and integrated pressurized water reactors (IPWR). These systems face dynamic operational challenges due to load-following requirements and rapid start-up/shutdown cycles. Compared to natural circulation steam generators, OTSGs exhibit lower thermal inertia and material content, leading to heightened sensitivity to thermodynamic fluctuations. This study proposes a novel sliding boundary lumped parameter model for OTSG operational control, derived from mass, momentum, and energy conservation principles. The model simplifies existing frameworks by reducing the number of governing differential equations from 11 to 4 while preserving accuracy. Numerical validation using a NuScale-type IPWR demonstrates that the model captures key thermohydraulic behaviors, including superheated section dynamics and open-loop responses under transient conditions. This work provides a foundation for real-time control system design and fault detection in SMR applications.