Thermal-Hydraulic Analysis of Water-Water Heat Exchanger Under Low Flow Conditions Using CFD Code
NURETH-14 - 2011 September 25-30


Presented at:
NURETH-14
2011 September 25-30
Location:
Toronto, Canada
Session Title:
I1-1 Thermalhydraulics of Non Electricity Generating Nuclear Equipment

Authors:
Masahito Takano (Research Institute of Nuclear Engineering, University of Fukui, Japan)
Hiroyasu Mochizuki (Research Institute of Nuclear Engineering, University of Fukui, Japan)
  

Abstract

In order to establish the evaluation method of the local heat transfer in the intermediate heat exchanger (IHX) for a fast breeder reactor, a CFD analysis method has been applied to a heat exchanger with the primary and secondary water-loops. Analyses were conducted under the forced circulation and natural circulation conditions. For the forced circulation experiment with the Reynolds number at 104, a quasi-steady state condition is analyzed. For the natural circulationexperiment, an analysis is also conducted for a quasi-steady state condition where the Reynolds number is approximately 102. The calculated heat transfer coefficients are converted into the Nu numbers and compared with the experimental results. Good agreement is obtained between the analytical results and the test results. Temperature distributions by the calculation results with the 1-dimensional NETFLOW++ code and CFD code are compared with the test results. For the natural circulation condition, it is clarified that there is almost no temperature distribution in radial direction, and the temperature is distributed only in axial direction. The flow on the primary-side seems to be rectified by the group of the heat transfer tubes and the turbulence is suppressed. For the forced circulation condition, the flow on the primary-side of the heat exchanger is stabilized also. The present CFD evaluation method can be applied to the IHX of the fast reactor with complex flow system.

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