Liquid Waste Handling Facilities for a Conceptual Light Water Reactor Spent Fuel Reprocessing Complex

1979 ◽  
Vol 43 (2) ◽  
pp. 244-258 ◽  
Author(s):  
D. C. Witt ◽  
R. F. Bradley
1989 ◽  
Author(s):  
L.E. Thomas ◽  
L.A. Charlot ◽  
J.E. Coleman ◽  
R.W. Knoll

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.


1984 ◽  
Vol 44 ◽  
Author(s):  
John O. Barner ◽  
J. L. Daniel

AbstractThe Materials Characterization Center (MCC) provides characterized light-water reactor (LWR) spent fuel approved testing materials (ATMs) for use by experimenters in radionuclide release studies in support of repository licensing efforts. The characterization completed to date is described for MCC ATM-101, a Zircaloy-clad UO2 fuel from the H. B. Robinson, Unit 2, Assembly BO-5. ATM-101 is a moderate burnup, low-releasing (fission products in-reactor) spent fuel typical of the fuel that is expected to initially be placed in a repository.


1982 ◽  
Vol 58 (2) ◽  
pp. 271-293 ◽  
Author(s):  
Earl J. Wheelwright ◽  
William J. Bjorklund ◽  
Larry M. Browne ◽  
Garry H. Bryan ◽  
Langdon K. Holton ◽  
...  

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