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...
Main Authors: | , , , , , |
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Format: | Article |
Language: | English |
Published: |
Elsevier
2019-10-01
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Series: | Nuclear Engineering and Technology |
Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573319302207 |