![]() Sensitivity analysis is performed to investigate the influence on the heat transfer from key parameters. It is proven that the code developed can be used to design and analyze the thermal-hydraulic behavior. The model is verified with the design results of design code SG-33 and CEFR. Equal node enthalpy increment in a region is applied to enhance the numerical accuracy. The characteristic tube is divided into four regions: subcooled region, nucleate boiling region, film boiling region and superheated region. A steady-state thermal-hydraulic model is derived based on the mass, energy and momentum equations. Therefore, a suitable thermal-hydraulic code is necessary to assist its design and analysis. It is challenging to design such a steam generator. Phase change exists in the water/steam side and the thermal-hydraulic behavior is difficult to predict. The CFR600 steam generator with straight tubes consists of the evaporator and the superheater. Lots of efforts are being made to its Research and Development (R&D). China Fast Reactor (CFR) with 600 MW electric power is under development in China.
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