TY - GEN
T1 - A NUMERICAL STUDY ON THE BEHAVIORS OF GRAPHITE AEROSOL IN THE CONTAINMENT DURING A WATER INGRESS ACCIDENT OF HIGH TEMPERATURE GAS-COOLED REACTORS
AU - Fang, Zhu
AU - Zhang, Yiyang
AU - Wang, Yating
AU - You, Zhikai
AU - Sun, Libin
AU - Wu, Xinxin
N1 - Publisher Copyright:
Copyright © 2022 by ASME.
PY - 2022
Y1 - 2022
N2 - The graphite dust is a special problem for pebble-bed high temperature gas-cooled reactors (HTGR), due to the close coupling with the fission products. A large fraction of graphite particles deposit on the tube bundles of steam generator (SG) due to the particle-vortex interaction and thermophoresis effect. Once a water-ingress accident occurs, the graphite dust may resuspend due to the rapid change of flow field. A certain fraction of resuspended dust, together with some fission products, could be discharged to the containment if the overpressure protection of the primary circuit is triggered. The distributions of deposited and airborne particles in the containment are crucial for the safety analysis and source term evaluation. In this work, we use a Eulerian-Lagrangian method to numerically study the transport and deposition behaviors of graphite aerosol in the full-scale containment during a water-ingress accident. Particularly, the effects of highly irregular shape of graphite particles on the particle-wall and particle-fluid interactions are incorporated. The statistical results that as the tracking time increases, the deposition rate first drops rapidly and then exponentially decreases. The deposition fraction is 80.38% for the floors, 9.83% for the shell of the containment, and 3.55% for other surfaces. Only 6.24% of particles are suspended in the air. As the particle size increases, the deposition fraction increases first and then decreases, reaching a maximum value at 3 μm. We also discuss the effect of the down direction of overpressure relief outlet on particle deposition. The result shows a fraction of 11.68% of airborne particles, which is about 2 times than that of the up direction. Our simulation not only demonstrates that the containment has a good capability to retain the graphite dust in a water-ingress accident scenario, but also provides a support for the engineering design of the overpressure relief system of HTGRs.
AB - The graphite dust is a special problem for pebble-bed high temperature gas-cooled reactors (HTGR), due to the close coupling with the fission products. A large fraction of graphite particles deposit on the tube bundles of steam generator (SG) due to the particle-vortex interaction and thermophoresis effect. Once a water-ingress accident occurs, the graphite dust may resuspend due to the rapid change of flow field. A certain fraction of resuspended dust, together with some fission products, could be discharged to the containment if the overpressure protection of the primary circuit is triggered. The distributions of deposited and airborne particles in the containment are crucial for the safety analysis and source term evaluation. In this work, we use a Eulerian-Lagrangian method to numerically study the transport and deposition behaviors of graphite aerosol in the full-scale containment during a water-ingress accident. Particularly, the effects of highly irregular shape of graphite particles on the particle-wall and particle-fluid interactions are incorporated. The statistical results that as the tracking time increases, the deposition rate first drops rapidly and then exponentially decreases. The deposition fraction is 80.38% for the floors, 9.83% for the shell of the containment, and 3.55% for other surfaces. Only 6.24% of particles are suspended in the air. As the particle size increases, the deposition fraction increases first and then decreases, reaching a maximum value at 3 μm. We also discuss the effect of the down direction of overpressure relief outlet on particle deposition. The result shows a fraction of 11.68% of airborne particles, which is about 2 times than that of the up direction. Our simulation not only demonstrates that the containment has a good capability to retain the graphite dust in a water-ingress accident scenario, but also provides a support for the engineering design of the overpressure relief system of HTGRs.
KW - Containment
KW - deposition
KW - Graphite dust
KW - High-temperature gas-cooled reactor
KW - Transport
KW - Water-ingress accident
UR - https://www.scopus.com/pages/publications/85143202424
U2 - 10.1115/ICONE29-929550
DO - 10.1115/ICONE29-929550
M3 - 会议稿件
AN - SCOPUS:85143202424
SN - 9784888982566
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - Computational Fluid Dynamics (CFD) and Applications
PB - American Society of Mechanical Engineers (ASME)
T2 - 2022 29th International Conference on Nuclear Engineering, ICONE 2022
Y2 - 8 August 2022 through 12 August 2022
ER -