Application of the risk oriented accident analysis methodology (ROAAM) to severe accident management in the AP600 advanced light water reactor

1998 ◽  
Vol 62 (1-2) ◽  
pp. 51-58 ◽  
Author(s):  
J.H Scobel ◽  
T.G Theofanous ◽  
S.W Sorrell
Keyword(s):  
Light Water Reactor ◽  
Severe Accident ◽  
Accident Analysis ◽  
Light Water ◽  
Water Reactor ◽  
Analysis Methodology ◽  
Accident Management

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
Keyword(s):  
Water Hammer ◽  
Gas Production ◽  
Light Water Reactor ◽  
Severe Accident ◽  
Light Water ◽  
Water Reactor

scholarly journals Investigation on Aerosol Pool Scrubbing Model During Severe Accidents

2021 ◽  
Vol 9 ◽  
Author(s):  
L. W. He ◽  
Y. X. Li ◽  
Y. Zhou ◽  
S. Chen ◽  
L. L. Tong ◽  
...  
Keyword(s):  
Bubble Size ◽  
Nuclear Power ◽  
Predictive Ability ◽  
Decontamination Factor ◽  
Light Water Reactor ◽  
Severe Accident ◽  
Spent Fuel ◽  
Analysis Model ◽  
Light Water ◽  
Water Reactor

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.

Modeling of Cesium Release from Light Water Reactor Fuel Under Severe Accident Conditions

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 ◽  
...  
Keyword(s):  
Reactor Fuel ◽  
Light Water Reactor ◽  
Severe Accident ◽  
Light Water ◽  
Water Reactor ◽  
Accident Conditions
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