The simulation of the light-water reactor (LWR) Aerosols Containment Experiment (LACE) LA4 experiment, which investigates thermohydraulic and aerosol behavior within a nuclear power plant containment, using the severe accident analysis code SPRUCE. Conducted at the Containment Systems Test Facility (CSTF) in Hanford Engineering Development Laboratory, the LACE LA4 experiment serves as a representative case of the thermohydraulic conditions and aerosol behavior in the containment of a LWR under severe accident scenarios with a containment late failure and aerosol release. The simulation is conducted by employing gaseous injection and aerosol injection boundary conditions. The outcomes, which encompass detailed thermohydraulics within the test facility and the mass profile of aerosols in the atmosphere, are meticulously compared with the experimental data to validate the accuracy and reliability of the SPRUCE code. This validation process is crucial for ensuring the code's applicability in predicting severe accident scenarios and supporting nuclear safety assessments.

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Simulation of Thermohydraulics and Aerosol Behavior in LACE LA4 via SPRUCE

  • Pingwen Ou,
  • Chao Guo,
  • Yong Ouyang,
  • Peng Chen

摘要

The simulation of the light-water reactor (LWR) Aerosols Containment Experiment (LACE) LA4 experiment, which investigates thermohydraulic and aerosol behavior within a nuclear power plant containment, using the severe accident analysis code SPRUCE. Conducted at the Containment Systems Test Facility (CSTF) in Hanford Engineering Development Laboratory, the LACE LA4 experiment serves as a representative case of the thermohydraulic conditions and aerosol behavior in the containment of a LWR under severe accident scenarios with a containment late failure and aerosol release. The simulation is conducted by employing gaseous injection and aerosol injection boundary conditions. The outcomes, which encompass detailed thermohydraulics within the test facility and the mass profile of aerosols in the atmosphere, are meticulously compared with the experimental data to validate the accuracy and reliability of the SPRUCE code. This validation process is crucial for ensuring the code's applicability in predicting severe accident scenarios and supporting nuclear safety assessments.