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Analysis of SMART reactor core using COREDAX code

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1 Author(s)
Jaejun Lee ; KINS, South Korea

The 3-D neutronics code COREDAX has been developed for x-y-z geometry based on AFEN (Analytic Function Expansion Nodal) method for SMART(System-integrated Modular Advanced ReacTor), a small sized integral type pressurized water reactor with the thermal power of 330 MWt, which is under development in Korea. The COREDAX code was applied to the SMART reactor core, which is smaller and different core comparing with the conventional commercial nuclear power plants. For nuclear cross section generation, HELIOS lattice code was used. Several steady and transient calculations were performed by the COREDAX code and their results are compared with those of reference calculations and standard safety analysis report of the SMART for regulatory purpose.

Published in:

Energetics (IYCE), Proceedings of the 2011 3rd International Youth Conference on

Date of Conference:

7-9 July 2011