1. Asok Kumar M 1990 THYC-3D, A computer code for thermal hydraulic analysis. Proc. 4th Int. Conf. on Simulation Methods in Nuclear Engineering, Montreal
2. Azarian M, Astegiano J C, Tenchine D, Lacroix M, Vidard M 1990 Sodium thermal-hydraulics in the pool LMFBR primary vessel. Nuclear Eng. and Design 124: 417–430
3. CFX ( http://www.ansys.com/products/fluid-dynamics/cfx ).
4. Chetal S C, Bhoje S B, Kale R D, Rao A S L K, Mitra T K, Selvaraj A, Sethi V K, Sundaramoorthy T R, Balasubramaniyan V, Vaidyanathan G 1995 Conceptual design of heat transport system and components of PFBR — NSSS. Proc. of IAEA Tech. Committee Meeting. Conceptual Design of Advanced Fast Reactors, IAEA-TECDOC-907, Kalpakkam, India, 11-132
5. FLUENT ( http://www.fluent.com ).