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The sodium-cooled fast reactor (SFR), a fourth-generation advanced nuclear energy system and the most technologically mature fast reactor design worldwide, employs liquid sodium as a primary coolant to extract core thermal energy and generate superheated steam through steam generators (SGs) for turbine operation. A critical safety concern arises from potential rupture of SG heat transfer tubes separating sodium and water/steam circuits, which could trigger violent sodium-water reactions (SWRs) upon contact between high-pressure steam and liquid sodium. During the initial phase of tube failure characterized by minimal rupture size and low leakage rates, the SWR exhibits relatively moderate progression. Timely detection of small-leakages and implementation of engineered safety features during this critical phase can effectively mitigate accident escalation, significantly reducing radiological consequences while maintaining reactor operational integrity. Accordingly, SFR designs incorporate dedicated small-leak detection subsystems within SG tube rupture protection systems. This study investigates the performance verification of a multi-module SG’s small-leakage SWR detection system through hydrogen injection experiments simulating accident-generated hydrogen transport in sodium circuits. The experimental methodology comprises two phases: (1) Theoretical determination of hydrogen injection parameters through thermochemical analysis of SWR kinetics under small-leakage conditions, and (2) Systematic hydrogen injection tests within operational sodium systems. By strategically injecting hydrogen at various positions across multiple SG modules, the research successfully mapped hydrogen diffusion pathways corresponding to different leakage locations. The experimental results validate the detection subsystem’s responsiveness and confirm the logical soundness of the small-leakage alarm algorithm. These findings provide critical experimental validation for optimizing SWR mitigation strategies and enhancing operational safety in prototype SFR facilities.

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Pilot Study of Detection System for Small Leakage of Sodium Water Accident in Multi-Module Steam Generator

  • 会议论文

  • 发表日期：

    2026年

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  • Jundong Qian,
  • Bin Hou,
  • Huanjun Zhu

摘要

The sodium-cooled fast reactor (SFR), a fourth-generation advanced nuclear energy system and the most technologically mature fast reactor design worldwide, employs liquid sodium as a primary coolant to extract core thermal energy and generate superheated steam through steam generators (SGs) for turbine operation. A critical safety concern arises from potential rupture of SG heat transfer tubes separating sodium and water/steam circuits, which could trigger violent sodium-water reactions (SWRs) upon contact between high-pressure steam and liquid sodium. During the initial phase of tube failure characterized by minimal rupture size and low leakage rates, the SWR exhibits relatively moderate progression. Timely detection of small-leakages and implementation of engineered safety features during this critical phase can effectively mitigate accident escalation, significantly reducing radiological consequences while maintaining reactor operational integrity. Accordingly, SFR designs incorporate dedicated small-leak detection subsystems within SG tube rupture protection systems. This study investigates the performance verification of a multi-module SG’s small-leakage SWR detection system through hydrogen injection experiments simulating accident-generated hydrogen transport in sodium circuits. The experimental methodology comprises two phases: (1) Theoretical determination of hydrogen injection parameters through thermochemical analysis of SWR kinetics under small-leakage conditions, and (2) Systematic hydrogen injection tests within operational sodium systems. By strategically injecting hydrogen at various positions across multiple SG modules, the research successfully mapped hydrogen diffusion pathways corresponding to different leakage locations. The experimental results validate the detection subsystem’s responsiveness and confirm the logical soundness of the small-leakage alarm algorithm. These findings provide critical experimental validation for optimizing SWR mitigation strategies and enhancing operational safety in prototype SFR facilities.