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[en] This paper describes a simplified model to predict the fluid velocity in the external channels of the tube bundle of a vertical once-through steam generator. The model is applied to analyse the three dimensional velocity distribution in a tube bundle cooled by steady state, single phase sodium flow. Results are presented for both a 45 MW and a 225 MW steam generator, including spacer grids and obstructions (to prevent the flow by-pass in the border channels). (author)
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British Nuclear Energy Society, London; 342 p; ISBN 0 7277 0269 6; 
; 1986; p. 23-27; British Nuclear Energy Society; London (UK); 3. international conference on boiler dynamics and control in nuclear power stations; Harrogate (UK); 21-25 Oct 1985; Price Pound65.00
; 1986; p. 23-27; British Nuclear Energy Society; London (UK); 3. international conference on boiler dynamics and control in nuclear power stations; Harrogate (UK); 21-25 Oct 1985; Price Pound65.00