Experimental and CFD simulations of fluid flow and temperature distribution in a natural circulation driven Passive Moderator Cooling System of an advanced nuclear reactor

Author:

Pal Eshita,Kumar Mukesh,Nayak Arun K.,Joshi Jyeshtharaj B.

Publisher

Elsevier BV

Subject

Applied Mathematics,Industrial and Manufacturing Engineering,General Chemical Engineering,General Chemistry

Reference46 articles.

1. A numerical and three-dimensional analysis of steady state rectangular natural circulation loop;Angelo;Nucl. Eng. Des.,2012

2. Arsene, R., Prisecaru, I., Nicolici, S., 2013. Improvement of the Thermalhydraulic Characteristics in the Calandria Vessel of a CANDU 6 Nuclear Reactor, U.P.B. Sci. Bull., Series C, 75 (4).

3. Baek, W.P., Spinks, N.J., 1994. CANDU Passive heat rejection using the moderator. In: Proceedings of the International Conference on New Trends in Nuclear System Thermalhydraulics. Pisa, Italy. May 30–June 2.

4. Similitude considerations for modeling nuclear reactor blowdowns;Carbiener;Trans. Am. Nucl. Soc.,1969

5. CFX-4.2: Solver Manual, 1997. CFX International, United Kingdom.

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