Authors: A. Samantara, K. Natesan
Year: 2026
Industry: Nuclear & SMR
Keywords: Use FSE, Steady state, Transient, Dynamic, SFR, Validation
ABSTRACT
Post shutdown decay heat removal from nuclear reactor core is essential for reactor safety. This is achieved by safety grade decay heat removal (SGDHR) system in Indian fast reactor. The performance of SGDHR system is studied by developing thermal-hydraulics model in system dynamics code Flownex. The model is validated against in-house SADHANA experiment facility for both steady state and transient conditions. Steady state performance of the system is predicted well and maximum deviation in heat removal capacity is less than 5%. Transient performance of the system is validated for three events, viz., sudden opening of damper, reactor shutdown following SCRAM (safety control rod accelerated movement) and station blackout accident. Natural circulation flow rate and decay heat removal capacity are predicted well in the model. This will help in increasing the confidence level of the model for decay heat removal application in prototype fast breeder reactor (PFBR).