Critical Heat Flux Calculation by ALTHAM C12 Code

26. 6. 2019

The second stage of the project no. CZ.01.1.02/0.0/0.0/17_102/0011478 “Application of Codes and Correlations for the Calculation of Critical Heat Flux in Nuclear Reactors” was started on January 1st, 2019. The project is co-financed by “Operational Programme Enterprise and Innovations for Competitiveness (OPPIK)”. In the framework of the project TES experts in cooperation with the Brno University of Technology have developed and evaluated methodology procedures for safety analyses related to the critical heat flux in nuclear reactors of PWR type with square geometry of nuclear fuel.
The computation will be performed with ALTHAM C12 program developed by ALVEI. Experimental data for the validation of the computational code and related methodology was obtained from international NEA and EPRI databases.