Author:
Aghaie M.,Zolfaghari A.,Minuchehr A.,Shirani A.,Norouzi A.
Subject
Nuclear Energy and Engineering
Reference22 articles.
1. Basile, D., et al., 1999. COBRA-EN: an Upgraded Version of the COBRA-3C/MIT Code for Thermal–Hydraulic Transient Analysis of Light Water Reactor Fuel Assemblies and Cores. Report 1010/1, ENELCRTN, Milano.
2. Steady-state thermal hydraulic and safety analyses of a proposed mixed fuel (HEU&LEU) core for Pakistan Research Reactor-1;Bokhari;Annals of Nuclear Energy,2004
3. Nuclear Heat Transport;El-Wakil,1971
4. A problem in the COBRA-EN code related to the void fraction calculation;Braz Filho;Annals of Nuclear Energy,2005
5. Hagrman, D.L., Reymann, G.A., Mason, R.E. MATPRO-Version 11 (Revision 2): a Handbook of Materials Properties for Use in the Analysis of Light Water Reactor Fuel Rod Behavior. Idaho National Engineering Laboratories, NUREG/CR-0497 and TREE-1280, Revision 2, August 1980.
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