Development and validation of reactor nuclear design code CORCA-3D

The advanced node core code CORCA-3D is one of the independent developed codes of NPIC for the nuclear reactor core design. CORCA-3D code can calculate the few-group cross section, solve the 3D diffusion equations, consider the thermal-hydraulic feedback, reconstruct the pin-by-pin power. It has lot...

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Bibliographic Details
Main Authors: Ping An, Yongqiang Ma, Peng Xiao, Fengchen Guo, Wei Lu, Xiaoming Chai
Format: Article
Language:English
Published: Elsevier 2019-10-01
Series:Nuclear Engineering and Technology
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573319302207