CFD simulation for the optimal design and utilization of experiment to research the flow process in PWR

Author:

Chen Guangliang,Zhang Zhijian,Tian Zhaofei,Dong Xiaomeng,Wang Yafeng

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference17 articles.

1. Ansys Fluent, 2013. Ansys Fluent 15.0 Documentation.

2. Development of a subchannel void sensor and two-phase flow measurement in 10×10 rod bundle;Arai;Int. J. Multiphase Flow,2012

3. Blowe, T.N., Kang, S.K., Hassan, Y.A., 2015. CFD methodologies for a PWR fuel rod assembly. 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16). Chicago, IL, USA, [CD-ROM].

4. Hydraulic benchmark data for PWR mixing vane grid;Conner;Nucl. Eng. Des.,2013

5. Experimental benchmark data for PWR rod bundle with spacer-grids;Dominguez-Ontiveros;Nucl. Eng. Des.,2012

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