NUMERICAL INVESTIGATIONS AND ANALYSES ON DEBRIS BED COOLABILITY AND RE-CRICALITY FOR JAPAN SODIUM COOLED FAST REACTOR (JSFR)

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  • LI Chun-Yen
    The Department of Nuclear Engineering and Management, The University of Tokyo
  • TAKATA Takashi
    Oarai Research & Development Institute, Japan Atomic Energy Agency
  • OKAMOTO Koji
    The Department of Nuclear Engineering and Management, The University of Tokyo

抄録

The in-vessel retention (IVR) of core disruptive accident(CDA) is of prime importance in enhancing safety characteristics of Japan Sodium Cooled Fast Reactor (JSFR). In the heat-removal phase, IVR failure is dominated by thermal boundary failures. One of the main factors of thermal boundary failure is the incompleteness of stable cooling due to the debris bed exceeding the coolable limit. The coolability of the debris bed is strongly affected by its condition such as the shape and inclined angle of debris bed, porosity, and the amount of discharged fuel/structure from core region, etc. Related parameter studies on the coolability of the debris bed were evaluated by preliminary analyses using the STAR CCM+ code, taking into account the natural circulation of the sodium coolant. On the other hand, the other factor to induce thermal boundary failure is severe power burst events from the debris bed in the heat-removal phase; therefore, re-criticality calculations via MCNP4 were also considered based on the alternative types of debris bed. These results can provide effective references for optimizing the performance of this multi-layer debris tray design in JSFR in the future.

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