MAAP5-CANDU DEVELOPMENT
36th Annual CNS Conference - 2016 June 19-22


Presented at:
36th Annual CNS Conference
2016 June 19-22
Location:
Toronto, Canada
Session Title:
Session T1A: Reactor Safety and Licensing 3

Authors:
J. Kennedy (Amec Foster Wheeler)
P. Maka (Amec Foster Wheeler)
M. Chai (Amec Foster Wheeler)
  

Abstract

MAAP-CANDU is an integral system analysis code for assessing the consequence of a severe accident in CANDU nuclear power plants. The current version of the code features simplifications, such as lumped models and coarse nodalization that enable a fast running code. Increased computer processing speeds now permit improved resolution in the code with less impact on run times. As a response to the Fukushima Daiichi accident, initiatives to improve severe accident modeling for different reactor types in various severe accident codes are currently underway internationally. Similarly, a development program was initiated by the CANDU Owners Group (COG) to enhance the MAAP5-CANDU tool suite. This paper provides an overview of the code improvements currently in progress. Specific requirements for each development item are discussed along with the challenges associated with implementing each item into the code. The benefits of these improved models to CANDU severe accident analysis are also highlighted.

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