Development of a decay heat removal analysis code for the sodium-cooled fast reactor

The decay heat removal capacity after emergency shutdown is one of the most important security indexes for sodium-cooled fast reactors. Dedicated decay heat removal system is in great need in analyzing the core decay heat removal capacity in designing sodium cooled fast reactor. In this paper, a decay heat removal analysis code in a unified development platform has been developed with modular programming, which contains the primary loop with components of core, inter-wrapper fluid and heat exchanger, as well as the decay heat removal loop with typical components in the sodium intermediate and air cooling circuit. Many studies have been conducted on code verification including international benchmark analysis and the comparison with the steady state of China Experimental Fast Reactor, which shows the results are in good agreement. Various kinds of transient calculation on the China Experimental Fast Reactor will be performed and the results will be compared with the experiments to validate the code further. (author)