Development of thermal-hydraulic analysis code of a helically coiled once-through steam generator based on two-fluid model

Author:

Chen Huandong,Chen Jiayue,Zhang Xiaoying

Funder

National Key R&D Program of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference32 articles.

1. Laminar flow and heat transfer in helically coiled tubes with substantial pitch;Austen;Exp. Therm Fluid Sci.,1988

2. PWR plant and steam generator dynamics;Bruens;Mat. Res.,1981

3. Campolunghi F., Cumo M., Ferrari G., Palazzi G., 1977. Full scale tests and thermal design correlation for coiled once-through steam generators. National heat transfer conference, United States, 73:164, 215-227.

4. Cinotti, L., Bruzzone, M., Meda, N., Corsini, G., Lombardi, C. V., Ricotti, M., Conway, L. E., 2002. Steam generator of the international reactor innovative and secure (IRIS). In Proc. 10th International conference on nuclear engineering (ICONE-10), 14-18.

5. A scheme of correlation for frictional pressure drop in steam–water two-phase flow in helicoidal tubes;Colombo;Chem. Eng. Sci.,2015

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