Multi-module program for small-leak sodium-water reaction analysis in steam generators of sodium-cooled fast reactors

摘要

To analyze the process of a small-leak sodium-water reaction (SWR) in the secondary loop of the steam generator (SG) in sodium-cooled fast reactors (SFRs), a multi-module program is developed herein. This program is developed by evaluating the models of heat transfer tube self-wastage, target tube wastage, and hydrogen migration and dissolution, which are involved in the small-leak SWR accident caused by a heat transfer tube with leakage in a single-module SG. The developed program could be used to investigate the time of occurrence of the heat transfer tube self-wastage, adjacent tube wastage, and the response time of the hydrogen concentration detectors at different leakage rates. The program can further provide the reasonable positions of hydrogen concentration detectors. The results of this study provide a reference for designing the secondary loops of smallleak accident protection systems for SFRs.