Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Thermal striping benchmark exercise: Thermal hydraulic analysis of the Phenix fast reactor secondary pipework T-junction

Abstract

A thermal hydraulic analysis of the T-junction which forms the basis of the Thermal Striping Benchmark Exercise has been carried out using the CFX4 CFD code together with an analytical boundary layer attenuation model. The mean momentum, temperature, turbulence and temperature variance fields were determined using CFX4 and the results were used to construct the spectra of the temperature fluctuations at the positions of the thermocouples. Application of a boundary layer attenuation model generated spectra at both the inside and outside surfaces of the pipe wall. These spectra were used to synthesise fluctuating temperature histories in the fluid and on both surfaces of the pipe wall at the thermocouples which showed significant temperature variances. Out of the 15 thermocouples, significant variances were found only at Thermocouples 1,2,3,6 and 15.

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Reference:

Final report of a co-ordinated research project 1996-1999

International Atomic Energy Agency, Vienna (Austria)

IAEA-TECDOC--1318, pp:2060-226