Montreal Nuclear Services

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Heat Transfer Analysis of MACSTOR-400 for Qinshan and Wolsong NPP

CANDU-6

SCOPE

Perform heat transfer analyses for MACSTOR-400 spent fuel dry storagesystem at the Wolsong and Qinshan nuclear power plants. 

DESCRIPTION

To be compliant with regulatory requirements KHNP and TQPNC had to demonstrate that the temperatures of the fuel, cylinders and concrete meet the design and safety acceptance criteria. 


A CATHENA model of the MACSTOR-400 was developed and tested against available data on a similar module in operation at the Gentilly-2 site in Canada.  A CATHENA model of the basket was also developed.


The work consisted of identifying credible and limiting accident scenario, define the methodology, develop the required models, perform analyses and verify that results meet the acceptance criteria.  A heat transfer analysis of the fuel basket was also performed to predict the maximum fuel temperatures for input to the oxidation analysis.


The work was contracted to AECL (Atomic Energy of Canada Ltd).  Gilles Sabourin was the analyst. 


NOTE:  This work was performed / lead by MNS personnel during their previous employment


OUTCOME


  • Model of MACSTOR-400.
  • Calculations of fuel, cylinders and concrete temperatures under normal and abnormal conditions

  • Two Methodology Reports and three Analysis Reports


DISCIPLINES

  • Heat Transfer


CLIENT

TQNPC, China

KHNP, Korea


Timeframe

2005


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