Validation of Subchannel Code Kamui: Analysis of Outlet Temperature Profiles of a 19-Pin Test Assembly
NURETH-14 - 2011 September 25-30

Presented at:
2011 September 25-30
Toronto, Canada
Session Title:
B3-3 Core Thermalhydraulics and Subchannel Analysis

Syeilendra Pramuditya (Tokyo Institute of Technology)
Hisashi Ninokata (Tokyo Institute of Technology)


Thermal hydraulic analysis of a Sodium-cooled Fast Reactor test assembly has been performed by employing subchannel analysis code KAMUI. The code has been updated by incorporating some recent physical models for pressure drop and coolant mixing. Performance of several conventional flow resistance and mixing models was assessed, by comparing predicted outlet temperature profiles against available experimental data. The calculations were carried out for high, transitional, and low Reynolds number regions. The prediction capability of the code for a wire-wrapped bundle has been successfully demonstrated in this paper.

Individual Conference-Paper Copies (Electronic Where Available):

  • For CNS members, the first 5 copies per calendar year are free, and additional copies are $10 each.
  • For non-members, the price is $25 for the first Conference-paper copy in a request, and $10 each for additional copies of papers in the same conference and in the same request.
  • Contact the CNS office to order reprints.