The Effect of a CANDU Fuel Bundle Geometric Variation on Thermal Hydraulic Performance
International Conference on the Future of Heavy Water Reactors - 2011 October 02-05


Presented at:
International Conference on the Future of Heavy Water Reactors
2011 October 02-05
Location:
Ottawa, Canada
Session Title:
Thermalhydraulics (I)

Authors:
Jun Ho Bae (Korea Atomic Energy Research Institute)
Joo Hwan Park (Korea Atomic Energy Research Institute)
  

Abstract

The effect of fuel bundle geometry using the subchannel code ASSERT has been evaluated to enhance the thermalhydraulic performance. Based on the configuration of a standard 37- element fuel bundle, the element diameter in center ring has been changed while those of other rings are kept as the original size.

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