Conference
Predictions of critical heat flux using the ASSERT subchannel code for a CANFLEX variant bundle
Abstract
The ASSERT subchannel code developed by AECL has been applied as a design-assist tool to the advanced CANDU®1 reactor fuel. Based primarily on the CANFLEX®2 fuel bundle, several geometry changes (such as element sizes and pitch-circle diameters of various element rings) were examined to optimize the dryout power and pressure-drop performances of the new fuel. An experiment was performed to obtain dryout power measurements for verification of …
Authors
Onder EN; Leung LKH; Rao YF
Publication Date
December 1, 2007
Conference proceedings
Proceedings 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics Nureth 12