scholarly journals Water Hammer Caused by Rapid Gas Production in a Severe Accident in a Light Water Reactor

2005 ◽  
Vol 48 (1) ◽  
pp. 48-55 ◽  
Author(s):  
Fujio INASAKA ◽  
Masaki ADACHI ◽  
Kohki SHIOZAKI ◽  
Izuo AYA ◽  
Hideki NARIAI
2021 ◽  
Vol 9 ◽  
Author(s):  
L. W. He ◽  
Y. X. Li ◽  
Y. Zhou ◽  
S. Chen ◽  
L. L. Tong ◽  
...  

During a nuclear power plant severe accident, discharging gas mixture into the spent-fuel pool is an alternative containment depressurization measurement through which radioactive aerosols can be scrubbed. However, it is necessary to develop a code for analyzing the decontamination factor of aerosol pool scrubbing. This article has established the analysis model considering key aerosol pool scrubbing mechanisms and introduced the Akita bubble size relationship. In addition, a code for evaluating the decontamination factor of aerosol pool scrubbing was established. The Advanced Containment Experiment and Light Water Reactor Advanced Containment Experiment were simulated with the code considering different bubble sizes of the Akita model and MELCOR default value to verify the suitability of the Akita bubble size model for simulating aerosol pool scrubbing. Furthermore, the simulation results were compared with the results analyzed by MELCOR code and COCOSYS code from literature, and equivalent predictive ability was observed. In addition, a sensitivity analysis on bubble size was conducted, and the contribution of different behaviors and mechanisms has been discussed. Finally, the bubble breakup equation was revised and verified with the conditions of the multi-hole bubbler in the Advanced Containment Experiment and Light Water Reactor Advanced Containment Experiment.


1995 ◽  
Vol 109 (1) ◽  
pp. 39-53 ◽  
Author(s):  
Anne C. Harnden-Gillis ◽  
Brent J. Lewis ◽  
William S. Andrews ◽  
Peter L. Purdy ◽  
Morris F. Osborne ◽  
...  

Author(s):  
Kiyofumi Moriyama ◽  
Hyun Sun Park ◽  
Mooneon Lee ◽  
Jin Ho Park

The process of the ex-vessel molten core cooling in a pre-flooded reactor cavity during a severe accident of a light water reactor includes complicated phenomena such as melt jet breakup, debris bed formation and cooling and the molten core-concrete interaction. The melt coolability and its impact on the containment consequences are dependent on the interactions among those phenomena. A simplified parametric model, COOLAP-II, covering the melt jet breakup, debris bed formation and cooling was developed for the synthetic assessment of the ex-vessel melt coolability. The model was validated on the melt breakup and initial cooling by comparison with a full-model for fuel-coolant interactions, JASMINE.


1997 ◽  
Vol 117 (2) ◽  
pp. 158-170 ◽  
Author(s):  
Volker Noack ◽  
Siegfried J. L. Hagen ◽  
Peter Hofmann ◽  
Gerhard Schanz ◽  
Leo K. Sepold

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