Loss of flow accident and its mitigation measures for nuclear systems with SCWR-M

Based on a revised version of RELAP5, which can be used for super-critical pressure calculation, a model of mixed spectrum SCWR (SCWR-M) system is established. To analyze the transient behavior of SCWR-M and develop mitigation measures during loss of flow accident (LOFA), some important parameters, e.g. reactor coolant pump (RCP) coast-down time, Reactor Pressure Vessel (RPV) upper water volume and safety injection flow, etc., are chosen for the parametric analysis. The results achieved so far indicate that the SCWR-M system design is feasible and promising. Three important mitigation measures for LOFA of SCWR-M are derived from the results: RCP coast-down time of more than 15 s, RPV upper water volume of more than 27 m3, and safety injection of more than 5% of the system design flow.

► A model of mixed spectrum SCWR system is established by a revised version of RELAP5.
► Some important parameters are chosen to analysis the SCWR-M during LOFA.
► Three important mitigation measures for LOFA of SCWR-M are derived from the results.