Core thermal hydraulics

Author:

Kolev Nikolay Ivanov

Publisher

Springer Berlin Heidelberg

Reference97 articles.

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2. Akiyama, Y., Hori, K., Miyazaki, K., Nishioka, H., Sugiyama, S.: Evaluation of the bundle void fraction measurement data of PWR fuel assembly. In: 3rd JSME/ASME Joint International Conference on Nuclear Engineering, Kyoto International Conference Hall, Kyoto, Japan, April 23-27, vol. 1, pp. 211–216 (1995)

3. Akiyama, Y., Hori, K., Miyazaki, K., Nishioka, H., Sugiyama, S.: Pressurized water reactor fuel assembly subchannel void measurement. Nucl. Technol. 112, 412–421 (2005)

4. Ambrosini, W., Andreussi, P., Azzopardi, B.J.: A physically based correlation for drop size in annular flow XE “annular flow”. Int. J. Multiphase Flow 17(4), 497–507 (1991)

5. Anglart, H., Nylund, O.: CFD application to prediction of void distribution in two phase bubbly flow in rod bundles. Nucl. Eng. Des. 163, 81–98 (1996)

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