Open access peer-reviewed chapter

A Literature Survey of Neutronics and Thermal-Hydraulics Codes for Investigating Reactor Core Parameters; Artificial Neural Networks as the VVER-1000 Core Predictor

By Farshad Faghihi H. Khalafi and S. M. Mirvakili

Submitted: October 13th 2010Reviewed: April 10th 2011Published: September 6th 2011

DOI: 10.5772/16521

Downloaded: 6668

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Farshad Faghihi H. Khalafi and S. M. Mirvakili (September 6th 2011). A Literature Survey of Neutronics and Thermal-Hydraulics Codes for Investigating Reactor Core Parameters; Artificial Neural Networks as the VVER-1000 Core Predictor, Nuclear Power - System Simulations and Operation, Pavel Tsvetkov, IntechOpen, DOI: 10.5772/16521. Available from:

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