1. Agostini, G., Era, A. and Premoli, A., Density measurements of steam-water mixtures flowing in a tubular channel under adiabatic and heated conditions, CISE Milan Report CISE-R-291, (1969).
2. Ahnesjö, M., Andersson, P., Corre, J.- Le, and Andersson, S., Tomographic reconstructions and predictions of radial void distribution in BWR fuel rod bundle with part-length rods, Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermaldydraulics (NURETH-16) (2015), pp. 829-840.
3. Akiyama, Y., Miyazaki, K., Nishioka, H. and Takeda, N., Total Evaluation of in Bundle void fraction measurement test of PWR Assembly.” Proceedings of the 4th International Conference on Nuclear Engineering (ICONE-4) (1996), pp. 801-811.
4. Anklam, T. M. and Miller, R. F., Void fraction under high pressure, low flow conditions in rod bundle geometry, Nuclear Engineering and Design, Vol. 75, No. 1 (1983), pp. 99-108.
5. Anoda, Y., Kukita, Y. and Tasaka, K., Void fraction distribution in rod bundle under high pressure conditions, Proceedings of ASME Winter Annual Meeting, Advance in Gas-Liquid flows (1990), pp. 283-289.