Abstract
The Helical Coil tube type once-through Steam Generator (HCOTSG) is being used in an increasing number of reactor installations. Due to its special geometrical structure, the fluid heat transfer in the tube is enhanced by centrifugal forces, and has the advantages of compact structure, tolerable expansion and flexible arrangement. This paper takes the lead-bismuth helical coil tube type once-through steam generator as the study subjects. A self-developed steady-state calculation program is used to obtain the distribution of the thermal parameters on the primary and secondary sides and the length of the different heat transfer zones and the length of the helical tubes. In order to accurately analyse these characteristics of the lead-bismuth HCOTSG, the uniform flow model was selected in this paper, and the heat transfer zone on the secondary side was divided into single-phase liquid, two-phase and superheated steam zones, and the heat transfer relationship equation suitable for use in the HCOTSG was selected for the relevant calculations. A computational analysis of the Russian BREST and European ELSY steam generators was carried out using the numerical model to verify the accuracy of the program. The validated program was used to carry out the steady-state thermal analysis for the lead-bismuth HCOTSG. The results showed that the performance of the designed steam generator met the design requirements. This program provided more options for subsequent analysis of the steam generator under different operating conditions.
