Paper Name |
Thermal-hydraulic Design and Analysis Code Development for Steam Generator of CFR600 |
Author |
Peiwei Sun, Zi Wang, Jianmin Zhang, Guanghui Su |
Publication/Completion Time |
2016-04-01 |
Magazine Name |
Annals of Nuclear Energy |
Vol |
90 |
Related articles |
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Paper description |
China Fast Reactor (CFR) with 600 MW electric power is under development in China. Lots of efforts are
being made to its Research and Development (R&D). The CFR600 steam generator with straight tubes
consists of the evaporator and the superheater. Phase change exists in the water/steam side and the thermal–
hydraulic behavior is difficult to predict. It is challenging to design such a steam generator.
Therefore, a suitable thermal–hydraulic code is necessary to assist its design and analysis. A steadystate
thermal–hydraulic model is derived based on the mass, energy and momentum equations. The
characteristic tube is divided into four regions: subcooled region, nucleate boiling region, film boiling
region and superheated region. Equal node enthalpy increment in a region is applied to enhance the
numerical accuracy. The model is verified with the design results of design code SG-33 and CEFR. It is proven
that the code developed can be used to design and analyze the thermal–hydraulic behavior.
Sensitivity analysis is performed to investigate the influence on the heat transfer from key parameters.
A preliminary design of CFR600 steam generator is presented using the developed code and reasonable
results are obtained. |