Abstract

The thermal-hydraulic performance analysis code, ISGA (Integrated Steam Generator Analyzer) for the design of the integrated steam generator concept of double tube bundle steam generator (DTBSG), which is considered to eliminate a SWR possibility fundamentally in a sodium-cooled fast reactor, was developed for three candidate configurations of tube bundles; the integrated double region, integrated single region and radially separated bundle types. To verify the ISGA code and to confirm the viability of the concept, comparisons to experimental data have been carried out. The effects of properties deviation to total heat transfer rate are negligible through the sensitivity studies. General tendency of the temperature profiles seems to be reasonable for integrated type of the DTBSG. The multidimensional effects of the helical tube bundle which includes the entrance effect result in slight discrepancy. The calculated heat transfer rate curve shows a good agreement with the experimental data for the three types of DTBSGs. In the integrated type DTBSG, the convection heat transfer is less dominant for the heat transfer mechanism of the medium flow than in the radially separated type DTBSG. The feasibility of the three candidate DTBSG concepts was demonstrated and the validity of the 1-dimensional thermal-hydraulic analysis code ISGA was shown with comparisons to experimental data.

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