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ISSN Online: 2377-424X

ISBN Print: 0-89116-130-9

International Heat Transfer Conference 6
August, 7-11, 1978, Toronto, Canada

EXPERIMENTAL DETERMINATION OF CLADDING TEMPERATURE FIELDS IN THE CRITICAL REGIONS OF ROD BUNDLES WITH TURBULENT SODIUM FLOW AND COMPARISON WITH CALCULATIONS

Get access (open in a dialog) DOI: 10.1615/IHTC6.3420
pages 29-34

要約

Being the first safety barrier, the rod claddings of reactor core elements constitute a highly loaded and hence extremely important structural element. Their reliable and optimum design determines the operating safety and the economy of the reactor system. This calls among others for the precise knowledge of the three-dimensional temperature fields under all operation conditions conceivable. Such temperature fields were determined experimentally with an LMFBR 19-rod bundle model in turbulent sodium flow by means of a measurement technique especially suitable for high temperature liquid metall cooling. The most important results of the investigations are reported and compared with other experiments, global and local calculations on indicating the boundary conditions to be taken into account. These are the most significant results:
- The claddings of the rods next to the duct wall show the highest azimuthal temperature variations; they are about 10 times higher then that of the rods located in the central bundle region.
- The comparison with similar experiments performed by SUBBOTIN et al shows among others the dominating influence of the cooling channel geometry in the duct wall zone on the temperature distributions in the cladding tubes.
- The calculations performed with the global "sub-channel" codes yield results which are too optimistic.
- The calculations using local "slugflow" codes yield results which are too conservative.
The adaption of both computation methods to the experiments presented and suitable coupling of them are necessary. The significant geometry parameter in the duct wall zone remains to be investigated in further experiments.