scholarly journals OECD MCCI Project: Category 4 Integral Test to Validate Severe Accident Codes: Core-Concrete Interaction Test Six (CCI-6) Test Plan (Rev. 6)

2010 ◽  
Author(s):  
M. T. Farmer ◽  
D. J. Kilsdonk ◽  
S. Lomperski ◽  
R. W. Aeschlimann
Author(s):  
Wei Wei ◽  
Kelin Qi ◽  
Fuchang Shan ◽  
Yanfang Chen ◽  
Fude Guo

This paper describes a mechanistic model of the molten core-concrete interaction (MCCI) process under severe accidents, and selects the Daya-Bay nuclear power plant as the research object to calculate and analyze the process of the MCCI when the station blackout (SBO), or loss of coolant (LOCA) severe accident serial is happened. The calculation results of this procedure are compared with the large-scale analysis programs MELCOR to verify the reasonableness and correctness of the model. The results indicate that the model present in this paper can simulate the MCCI process correctly and reasonably under multi-serial severe accidents.


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.


2011 ◽  
Author(s):  
M. T. Farmer ◽  
D. J. Kilsdonk ◽  
S. Lomperski ◽  
R. W. Aeschliman ◽  
S. Basu

2015 ◽  
Vol 2015.23 (0) ◽  
pp. _ICONE23-2-_ICONE23-2
Author(s):  
Kazuya Shimamura ◽  
Michitsugu Mori ◽  
Shuichiro Miwa ◽  
Hiroto Sakashita

2010 ◽  
Author(s):  
M. T. Farmer ◽  
D. J. Kilsdonk ◽  
R. W. Aeschlimann ◽  
S. Lomperski

2008 ◽  
Author(s):  
M. T. Farmer ◽  
D. J. Kilsdonk ◽  
S. Lomperski ◽  
R. W. Aeschlimann
Keyword(s):  

2017 ◽  
Vol 3 (2) ◽  
Author(s):  
Robert David

The thickness at which the calandria vault floor in a generic CANDU 6 nuclear reactor may collapse while undergoing molten core–concrete interaction (MCCI) was studied using an approximate analytical model and a finite-element model. It was confirmed that the collapse criterion of 0.45 m floor thickness that is currently used in severe accident analyses is adequate. The estimated timing of collapse is subject to uncertainty of several hours.


2011 ◽  
Author(s):  
M. T. Farmer ◽  
D. J. Kilsdonk ◽  
S. Lomperski ◽  
R. W. Aeschlimann ◽  
S. Basu
Keyword(s):  

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